INST2019 (International Nuclear Science and Technology Conference)

Centara Grand at Central Ladprao

Centara Grand at Central Ladprao

Chatuchak, Bangkok 10900, Thailand

inst2019 banner

Welcome to INST2019 conference (Feb 4-6, 2019, Bangkok, Thailand). 

Nuclear technology has played an important role in many aspects of our lives, including agriculture, medicine and healthcare, materials, environment, forensics, energy, and frontier advancement. The International Nuclear Science and Technology Conference (INST) aims to bring together scientists, engineers, academics and students to share knowledge and experiences about all aspects of nuclear sciences.

INST has evolved from a national conference series on nuclear science and technology that was held every two years in Bangkok for over a twenty-year period.

INST2019 is the third of the INST conference series organized by Thailand Institute of Nuclear Technology. It will be held under the slogan 'Nuclear for Better Life' and theme 'Innovation and Advanced Technology.'

The program of the 2019 event will consist of oral and poster sessions from contributed papers. Invited lectures will be given by international experts. The proceedings of the conference will be published in a peer-reviewed journal (IOP Journal of Physics: Conference Series).

Topics addressed include nuclear science and technology in the following areas:

  • Agriculture and Food (AGR)
  • Environment (ENV)
  • Industry (IND)
  • Instrument (INS)
  • Medical (MED)
  • Physics (PHY)
  • Safety (SAF)
  • Newton Neutron Applications (NNA)

On 5 Feb, Newton Neutron Applications Workshop will be held as part of INST2019 under TINT-STFC Newton Program on Skills for Large Facilities. The workshop aims for knowledge sharing from experienced UK researchers, and for strengthening the understanding and scientific capability of SEA researchers regarding the applications of neutron techniques.

We look forward to seeing you in Bangkok!


  •  Abstract submission (online form): 1 May-15 Aug 2018 (1 presentation/registration)
  • Nuclear Scientist Award nominations: 1 May-31 Aug 2018
  • Acceptance revision & notification: 31 Aug 2018 (noon)
  • Payment (early): 1 Sep - 15 Nov 2018 (extended)
  • Payment (regular): 16 Nov - 15 Dec 2018
  • Onsite cash payment is accepted in Thai Baht only:
    • Regular: 10,000 THB
    • Student: 3,500 THB
  • Full paper submission (optional): from 6-20 Feb 2019

Payment options (see Registration page for details):

For students, please send a photo of your student ID or proof of university registration to to qualify for the student rate.

  1. Online (credit card via Krungsri E-Payment, in US Dollar)
  2. Bank transfer (Thai Baht)
  3. On-site payement on 4 Feb 2019 (cash in Thai Baht)

Bank transfer information:

Bank of Ayudhya
Branch: Kasetsart University
Account type: Savings
Account number: 3741593305
Account name (Thai): เงินสนับสนุนการจัดประชุม วทน.
(Account name = Support for INST, is in Thai name only)

Bank Headquarters address: 1222 Rama III Road, Bang Phongphang, Yan Nawa, Bangkok 10120 Thailand

Please notify us by email after you've made payment.

Newton Neutron Applications Workshop
  • Alina A Rahman
  • Amares Chatt
  • Anawat Rittirong
  • Andreas Musilek
  • Apichate Maneewong
  • Apisara Charoensri
  • Apiwat Wisitsorasak
  • Atchararat Chaimuanwong
  • BaekSeok SEONG
  • Budsaraphorn Moonlek
  • Chanis Pornnumpa
  • Chunyapuk Kukusamude
  • Chunyapuk Kukusamude
  • Chutima Kranrod
  • Darunee Peekhunthod
  • Dhanaj Saengchantr
  • Doendara Malain
  • Dussadee Rattanaphra
  • Dussadee Rattanaphra
  • Hassan Mohd Hafiz
  • Hendrik Heijnis
  • Hnit Thit Shein
  • Jaruratana Eamsiri
  • Jatechan Channuie
  • Jiraporn Promping
  • Julia AbdulKarim
  • Jun Zhuang
  • Kampanart Silva
  • Kanokporn Boonsirichai
  • Kanokrat Tiyapun
  • Kasinee Hemvichian
  • Kemiga Kuepitak
  • Khanit MATRA
  • Kiadtisak Saenboonruang
  • kittithat thanakorphimol
  • Korawit Saeju
  • Kotchaphan Kanjana
  • Kritsada Kittimanapun
  • leeda Mitrayon
  • Malik Anjelh Baqiya
  • Manh Dung Ho
  • Manit Jitpukdee
  • Michiko Fukushima
  • Moleephan Dangprasert
  • muhammad rawi mohamed zin
  • Myo Zaw Htut
  • Nadiya Miftachul Chusna
  • Najet Mahmoudi
  • Narongchai Autsavapromporn
  • Nawin Juntong
  • Nopparit Somboonkittichai
  • Noppawan Rattanadecho
  • Ooraphan Chirayutthanasak
  • Orasa Onjun
  • Panchalee Prakongsil
  • Pannipa Noithong
  • Pathcharanan Tuanghirunwimol
  • Pattaranipa Gunhakoon
  • Pattra Lertsarawut
  • Phacharatouch Chaimongkon
  • Phacharatouch Chaimongkon
  • Phongphaeth Pengvanich
  • Pichayada Katemake
  • Pimpon Uttayarat
  • Pinyapach Tiamduangtawan
  • Piyanuch Orpong
  • Piyawan Srikongpan
  • Pongphanot Rindhatayathon
  • Poonnaphob Sopapan
  • Porama Thepsiri
  • pornrad srisawad
  • Prasong Kessaratikoon
  • Purit Quinram
  • Retno Asih
  • Roppon Picha
  • Rungsin Kongkerd
  • Ryuta Hazama
  • Saensuk Wetchagarun
  • Sangutid Thongsawad
  • sarayut khemngern
  • Sarinya Wongsanit
  • Sasikarn Nuchdang
  • Sasiphan Khaweerat
  • Saurabh Kabra
  • Sawitree Suayod
  • Sirilak Chookaew
  • Siriyaporn Sangaroon
  • Sompong Sriburee
  • ST. Ulfawanti Intan Subadra
  • Suchanya Junsen
  • Sujittra Phetwiset
  • Supalak Kongsri
  • Supoj Ua-apisitwong
  • Suputtra Visetpotjanakit
  • Surasak Sajjabut
  • Sy Minh Tuan Hoang
  • Tachatad Kulthananat
  • TaeJoo Kim
  • Tarika thumvijit
  • Teesit Varapaskul
  • Test General
  • Thadpong Chanton
  • Thawatchai Itthipoonthanakorn
  • Thiansin Liamsuwan
  • Thiansin Liamswan
  • Thiti Rungseesumran
  • Thitirat Rattanawongwiboon
  • Thititip Tippayamontri
  • Todsaporn Fuangrod
  • Tosaporn PASSADU
  • Vararas Khamvarn
  • Vichai Puripunyavanich
  • Vichai Puripunyavanich
  • Vithit Pungkun
  • wachiraporn pewlong
  • Wanatchaporn Arunmanee
  • Wanitch Limohpasmanee
  • Wannee Srinuttrakul
  • Waraporn Sudchai
  • Wasin Vechgama
  • Weerawat Pornroongruengchok
  • Wiranee Sriwiang
  • Worrakarn Wangwon
  • Yanin Sukjai
  • Yottana Tanakaran
  • Zaifol Samsu
Contact person
    • 07:30 08:30
    • 09:00 10:30
      Opening Ceremony
    • 10:30 11:10
      • 10:30
        21st Century Nuclear Technology Solutions to Environmental Problems. A Paradigm Shift from Observation to Solution Based Research. 40m

        It has been a tradition since the late 1950’s, that nuclear science and technology was applied to environmental studies. The use of natural as well as artificial radioactive tracers has been successfully applied to reconstructing past environmental change, groundwater recharge rates, environmental pollution studies, ecotoxicology on biota. This presentation will focus on the transition of observational measurements of radioactive decay of key-isotopes to advanced measurement systems. The technological transition from low throughput sample analysis towards high throughput with high precision and accuracy has led to a great leap and indeed paradigm shift in the application of nuclear technology to environmental problems. This paradigm shift will be illustrated by using some recent examples from climate, food quality and food provenance research.

        We will also show another paradigm shift and demonstrate that partnerships and collaborations to form multidisciplinary teams are paramount to tackle environmental issues of the 21st century. We will simultaneously demonstrate that research does not have international boundaries and that international collaboration and developing capabilities in less developed countries should be part of our daily activities.

        Speaker: Prof. Hendrik Heijnis (Leader Environmental Research, ANSTO)
    • 11:10 12:00
    • 12:00 13:30
      Lunch 1h 30m
    • 13:30 14:50
      Oral 1: Block I
      • 13:30
        Current Status and Objectives of Tokamak Fusion Research in China 30m

        China fusion research has been carried out in a wide range from nuclear fusion research to basic plasma physics since1950s. The fundamental physics, plasma control, diagnostics, plasma wall interaction, fusion martials and engineering relevant has been addressed. In parallel, the thriving fusion research team including engineering and physics is formed. The successful programs like EAST and HL-2A have proved opportunities to address new scientific and technological problems in support of ITER and CFETR research. Significant progress has been made in the last decades on both devices. The frame of China fusion program is now evolving from a small subject to a large national agenda. Strongly financial and policy support have been given by Chinese government. Coordinating strategies of short-term and long-term activities have been made among China domestic fusion organizations (ASIPP, SWIP, USTC, CAEP, HUST, DHU, SJTU, TH, PKU, ZJU, DUT and SCU). China, as a partner of ITER, is in the leading position among the participants in the ITER project in carrying out the procurement package parts system research. In addition, beyond ITER, the concept design of CFETR, aiming to bridge gaps between ITER and DEMO, is in the integrated design of physics and engineering.

        Speaker: Prof. Baonian Wan (ASIPP)
      • 14:00
        Overview of Recent Experimental Results from EAST Tokamak 30m

        The recent EAST experiment is overviewed. Significant progress in the development of plasma control mechanism and understanding the related physics for steady-state advanced high-performance H-mode plasmas have been achieved on EAST. The operational regime of beta has been extended. First demonstration of >100 seconds time scale long-pulse steady-state scenario with a good plasma performance (H98(y2) ~ 1.1) using the pure RF power heating and current drive. The synergy effect between the ECH and two LHW systems (2.45GHz and 4.6GHz) on EAST has been investigated for enhanced current driven and improved confinement quality. ELM suppression using the n=1 and 2 RMPs has been achieved in EAST and applied for development of the long-pulse H-mode scenario. Divertor particle and heat flux control using a low n rotating RMP field has been confirmed. Suppression of the W sputtering has been achieved by lowering the edge medium-Z impurity content (C, O, etc) and forming a mixture deposition on the surface of divertor target after the application of lithium wall conditioning. Preliminary 1.5-D simulations suggest that the on-axis ECRH will enhance the deposition of LHW power in the core region, which is beneficial to the effective core heating of the plasma.

        Speaker: Prof. Xianzu Gong (ASIPP)
      • 14:30
        Thermally Stable Nanocrystalline Tungsten-Titanium Alloy for a First Wall Fusion Reactor 20m

        The success of thermonuclear fusion reactors relies on the development of materials used for confining plasma in extreme conditions (high temperature and high pressure). Tungsten is one of the material choices which are known for a very high melting point, excellent mechanical strength, and high radiation resistance. However, these properties degrade under a high-temperature operation. It was recently reported that thermal stability of polycrystalline tungsten can be significantly improved by using titanium (Ti) segregations at the grain boundaries. The ultimate goal of this work is to systematically investigate the structures and phase formations of Ti segregations at the grain boundaries of tungsten. We first prepared W-48 at.%Ti alloy by using radio frequency magnetron co-sputtering. X-ray diffraction (XRD) measurement demonstrated that the W-48 at%Ti alloy had a body centered cubic with a lattice parameter of 0.326 nm, which was slight larger than a lattice parameter of a pure tungsten thin film (0.319 nm). While this result was consistent with a recent study (M. Callisti, Journal of Alloys and Compounds, 2018), it should be noted that the lattice parameter of our alloy specimen was greater than the one reported in the previous study (0.318 nm) due to higher amount of Ti content and the strain energy presented in the films. It suggested that the crystal structures of Ti segregations and W matrix might be exist in the alloy specimens annealed at 1000 ºC. Thus, the mechanical properties of the tungsten alloy is enhanced and his technique may be for fabricating the tungsten alloy in the first wall of fusion reactors.

        Speaker: Ms. Ooraphan Chirayutthanasak (Nanoscience and Nanotechnology Graduate Program, Faculty of Science, King Mongkut's University of Technology Thonburi, Thailand)
    • 14:50 15:50
      Poster 1: Poster Session I
      • 14:50
        $\textit{In vitro}$ Multiple Shoot Formation of a Radiation-Induced Aromatic Rice 1h

        Hom Rangsi was a photoperiod-insensitive mutant aromatic rice which was derived from fast-neutron irradiation of KDML105. This study aims to investigate effects of N6-benzyladenine (BA) on shoot regeneration of Hom Rangsi grown in vitro. Seeds of rice were surface-sterilized and cultured on MS solid medium without hormone supplements for 2 weeks. Then, the explants were transplanted on to MS medium supplemented with BA at 0, 5, 10, 15, 20, and 25 mg/L for multiple shoot induction. Shoots were successfully regenerated with the average yields of 2.00, 3.55, 3.55, 4.34, 4.45 and 5.38 shoots/seed, respectively. The optimal concentration of BA for multiple shoot induction of Hom Rangsi was 25 mg/L; the highest average regeneration rate was 5.38 shoots/seed.

        Keywords: mutant rice, breeding, in vitro, multiple shoot induction

        Speaker: Ms. Vararas Khamvarn (Thailand Institute of Nuclear Technology)
      • 14:50
        A Genetic Sexing Strain of the Oriental Fruit Fly, $\textit{Bactrocera dorsalis}$ (Hendel) 1h

        A genetic sexing strain (GSS) of the oriental fruit fly, Bactrocera dorsalis (Hendel), based on the pupal color have been developed in order to increase efficiency of fruit fly control by using sterile insect technique. To study the quality of GSS in comparison to the genetic-marker strain currently used in field operations both strains were reared with artificial diet at 27$^{\circ}$C and 80 ± 10 %RH, and pupal quality was assessed. Adult eclosion, flight ability and fertility of GSS were 69.57 ± 6.29, 53.14 ± 6.15 and 47.48 ± 1.43 % respectively, which were significantly lower than those of the genetic-marker strain. Adult eclosion, flight ability and fertility of the genetic-marker stain were 93.66 ± 3.56, 87.00 ± 3.70 and 60.48 ± 7.09 % respectively. To study the effects of irradiation, late pupae, 2 days before emergence, were irradiated with 70 and 90 Gy gamma ray. Sterility and competitiveness index of irradiated GSS at 70 and 90 Gy were 96.15 ± 5.25, 97.12 ± 5.57 % and 0.51 ± 0.04 , 0.39 ± 0.08 respectively. Despite its lower pupal quality, the GSS irradiated at 70 Gy can potentially be used in an SIT program due to its higher mating competition.

        Speaker: Mr. Thodsapon Thannarin (Thailand Institue of Nuclear Technology (Public Organization) )
      • 14:50
        A Study of Residence Time Distribution in a Lab Scale Stirred Tank Reactor Using Radiotracer Technique 1h

        The mixing characteristic of a chemical reactor can be studied through the resident time distribution (RTD) of the reactor. One major application of the RTD is to perform troubleshooting for a reactor in operation. The deviations from ideal mixing condition such as presence of stagnant region, bypassing of fluids in the system, blockage or failure of the devices in the reactor can be observed through its RTD. In this paper, the study of RTD in a lab scale stirred tank reactor using radiotracer technique is presented. A small scale stirred tank reactor is used to represent a reactor in industry. The objective of this work is to gain experience on the handling of RTD measurement using radiotracer as well as performing RTD analysis of stirred tank reactor with different flow conditions. Tc-99m solution is selected to use in this work due to its chemical property, its suitable half-life and its on-site availability. NaI detectors were placed along the pipelines in order to determine the RTD of the system. The RTD and the Mean Residence Time (MRT) of the reactor is calculated and analysed for the case of normal flow condition and the system with some blockages.

        Speaker: Mr. Anantachai Pechrak (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        An Overview of Utilization at Thai Research Reactor (TRR-1/M1) 1h

        In 2017-2018, Thai Research Reactor (TRR-1/M1) was completely renovated of the control and ventilation systems. At the present, the TRIGA Mark III 1.2 MW research reactor, while waiting for the operating license, is getting ready to resume its active operation for service and research purposes. With the maximum neutron flux in the central thimble of 10$^{13}$ n/cm$^2 \cdot$s, and many sample irradiation positions available, the reactor can be utilized in many fields as follows: isotope production (medical and industrial), neutron radiography, neutron activation analysis (small and large samples), gemstone coloration, reactor physics including burn-up measurements and calculations, material characterization and testing. TRR-1/M1 welcomes users from Thailand, ASEAN countries, as well as international community to collaborate.

        Speaker: Jatechan Channuie (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Analysis of Telescope Particle Shower Data as Signal Classification Method Development 1h

        Simulated signals at the MAGIC telescope array are used to develop classification methods for signals of high energy cosmic radiation from astronomical nuclear processes. The instances consist of two classes of signals: electromagnetic shower and hadronic shower. The signals are not immediately distinguishable by visual inspection. Of the ten available features, none can to be used as a single identification criterion. The public Monte Carlo dataset can be used to develop methods for radiation signal processing in nuclear engineering. In this study, a selected set of six different machine-learning algorithms are used to identify the signals. The results are compared to baseline models and to each other. Of the selected models, extreme gradient boosting and random forest yield better scores than the others. The method can be applied to many other nuclear research topics.

        Keywords: radiation signal identification, classification, cosmic ray, method development, particle shower, machine learning, cherenkov radiation

        Speaker: Dr. Roppon Picha (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Assessment of Pulsing Simulation of TRR-1/M1 Using PULSTRI Code 1h

        The study is aiming at performing a review and safety assessment of Thailand's research reactor, TRR-1/M1, TRIGA Mark-III in order to determine if it is justifiable to grant an operating license for the operator by comparing experimental data with results obtained from calculations as presented in Safety Analysis Report, SAR where the maximum reactivity insertion is 4.50. Modeling, analysing and evaluating reactivity insertion safety of TRR-1/M1 at different pulsing power using PULSTRI code to simulate rapid increase in reactivity values due to pulsing operation or reactivity insertion accident (RIA) as described in IAEA’s SSG20. The analysis has shown that the adiabatic temperatures for pulsing at nominal conditions with maximum inserted reactivity of 3.25 from SAR is below the safety limit temperature $1100^{\circ}$C of nuclear fuel and is thus safe.
        Keywords: Pulse operation, PULSTRI, Reactivity Insertion Accident, TRR-1/M1, SAR.

        Speaker: Mr. Suksit Sangkaew (Office of Atoms for Peace(OAP))
      • 14:50
        Comparison of Photostimulated Luminescence and Thermoluminescence Techniques for Detection of Irradiation in Herbs, Spices and Seasonings 1h

        Photostimulated luminescence (PSL) and thermoluminescence (TL) are proven methods used for detection of irradiated foods containing minerals adopted by the European Committee for Standardization (CEN) and the Codex Alimentarius Commission. However, the mineral composition in foods strongly affects the luminescence intensity which might result in the correctness of irradiation identification. This research aimed to explore the ability of both techniques to detect irradiation in herbs, spices and seasonings according to the European standard EN 13751 and 1788, respectively. Samples of paprika, garlic and seasonings powders obtained from a food product company in Thailand were irradiated with a cobalt-60 gamma ray at the dose of 0, 1, 2, 5 and 10 kGy. The inorganic minerals were extracted from samples by using high density potassium carbonate solution instead of the high cost sodium polytungstate solution. The results revealed that the PSL screening in non-irradiated paprika and garlics showed negative readings except two samples of non-irradiated seasonings which intermediate results were obtained. However 100% of samples were correctly identified based on their TL ratios. The results confirm that TL method can be successfully applied to identify irradiation in herbs, spices and seasonings, especially when their PSL screenings show intermediate or positive results.

        Speaker: Dr. Wanwisa Sudprasert (Department of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University)
      • 14:50
        Design and Model of Thickness Gauging System by Using Low Activity of Gamma Radiation 1h

        Gamma radiation gauging method is one of the nucleonic control systems which have been widely used in industrial fields to improve the quality of the products, optimize the processes and save energy and material. Gamma-ray transmission methods have been used in this study to determine the thickness of sample materials which is known density based on the attenuation law (Beer Lambert’s Law). In this study, Cs-137 gamma radiation source of current activity 2.6 MBq and the scintillation NaI(Tl) (1 inchx1 inch) detector was used for the measurement system. The measurement had been made very accurately by using a narrow collimated beam system, which effectively excluded correction due to the small angle and multiple scattering of photons with the created program Gamma Thickness Gauging System (GTGS) using with Cassy Modules and Matlab GUI. The created GTGS program also indicate the values of measured thickness of samples and intensity values, which are shown in the LCD display by Arduino Uno control board. This study can be applied in the industrial field for the quality control of the product materials.
        Keywords: gamma-ray transmission, thickness gauging, Cassy, Matlab,
        Arduino Uno, scintillation NaI(Tl) detector

        Speaker: Prof. Hnit Thit Shein (Nuclear physics lab, DSA)
      • 14:50
        Determination of Location and Volume of Accumulated Liquid under PIR Thermal Insulation using Neutron Radiation Techniques 1h

        The corrosion under insulation (CUI) is the common problem that can be found in the production pipelines of petroleum and petrochemical plants. The reason of occurrence could be from the accumulation of liquid such as rain or even the condensation of product inside the pipelines. This research aims to determine location and to approximate the volume of liquid accumulated though the true scale pipeline model using neutron radiation techniques. The model composed of a metal pipe, diameter 254 mm (10 in.) covered by polyisocyanurate (PIR) thermal insulation. The volume of liquid accumulated under the insulation can be varied, in order to determine the detectability of system. The neutron radiation techniques used in this research are neutron backscattering and neutron transmission. Neutron backscattering was used to determine the location of liquid whereas neutron transmission was used to estimate the volume of the liquid. The Am241-Be neutron source and He-3 neutron detector were fabricated inside single probe and connected to the radiation counter. Results of research indicated that neutron backscattering technique can locate the boundary of accumulated liquid along the circumference of pipe. The transmission technique provided results of measured volume deviated from setting up about 10%.

        Speakers: Mr. Dhanaj Saengchantr (Thailand Institute of Nuclear Technology (Public Organization)), Mr. Tosaporn Passadu (Thailand Institute of Nuclear Technology (Public Organization), Ms. Noppawan Rattanadecho (Thailand Institute of Nuclear Technology (Public Organization)
      • 14:50
        Developing and Upscaling of Functional Adsorbent by Radiation-Induced Grafting for Wastewater Treatment 1h

        A functional adsorbent with specific selectivity for heavy metals was prepared by radiation-induced grafting polymerization of bis [2-(methacryloyloxy) ethyl] phosphate (BMEP) onto polyethylene/poly propylene (PP-PE) non-woven fabric. Effects of monomer, solvent and radiation dose on degree of grafting were investigated. FTIR and SEM were used to characterize the prepared adsorbents as well as to confirm that the grafting polymerization was effective. Efficiency of heavy metal adsorption of the adsorbents were done by UV spectrophotometry, using a calibration curve made from standard CuCl$_2$ solution. Effects of degree of grafting (from 107 to 326%) on adsorption efficiency were analyzed. Results showed that degree of grafting in the range of 130 – 170% led to maximum efficiency of Cu$^{2+}$ adsorption in the range of 80 – 85%. These preliminary results were used for an upscaling of adsorbent preparation. A prototype for a fix-bed column (height = 35 cm, diameter = 3 cm) was designed. The adsorption capacity of Cu$^{2+}$ of the adsorbent using a prototype fix-bed column was 0.129 mg/cm$^2$, showing its potential to be utilized for removal of heavy metals in a portable wastewater treatment system.

        Speaker: Dr. Thitirat Rattanawongwiboon (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Development of Portable X-ray Fluoresce Spectrometry for Elements Analysis in Geological Samples 1h

        This study aims to develop the portable x-ray fluorescence spectrometry (pXRF) for quantitative analysis of major and minor elements in the geological samples. Eight geological certified reference materials (BCR-2: basalt, COQ-1: carbonatite, GSP-2: granodiorite, JA-1: andesite, JB-2: basalt, JG-1a: granodiorite, JG-2: granite and JSy-1: Syenite) were used to calibrate the analytical method. The samples were prepared by the pressed pellet method. Good agreement between the certified and measured values was achieved (R2 > 0.90) for Aluminium (Al), Calcium (Ca), Iron (Fe), Manganese (Mn), Potassium (K), Rubidium (Rb), Silicon (Si), Strontium (Sr), Titanium (Ti) and Yttrium (Y). The recalibration method was done for some elements such as Al, Ca, Fe, K, Si and Ti in order to improve their accuracy. The relative error for all elements were better than 20%. The geological samples collected from Phuket province, Thailand were determined by the developed-pXRF method. The concentration values range were Al (6.6-17.2%), Ca (0.6-2.9%), Fe (0.5-6.2%), K (0.9-5.4%), Mn (79.2-1294.8 ppm), Rb(179.6-1042.7 ppm), Si (21.4-32.7%), Sr (7.1-207.1 ppm), Ti (0.1-0.6%) and Y (13.8-453.0 ppm). The results of the developed-pXRF method were in good accordance with standard WDXRF method (%RSD < 20).

        Speakers: Mr. Kittithat Thanakorphimol (King Mongkut's University of Technology Thonburi.), Mr. Tachatad Kulthananat (King Mongkut's University of Technology )
      • 14:50
        Dye Adsorbent Prepared by Radiation-Induced Graft Polymerization of Acrylic Acid onto Carboxymethyl Cellulose 1h

        Gamma radiation was used to prepare a natural polymer-based adsorbent via radiation-induced grafting polymerization of acrylic acid (AA) onto carboxymethyl cellulose (CMC). Optimization of the grafting process was done by varying a number of parameters from radiation dose to amount of AA and CMC. Characterization by Fourier transform infrared spectroscopy (FTIR) and thermogravimetric analysis (TGA) confirmed a successful grafting of AA onto CMC, with a maximum grafting efficiency (GE) of 94%. The effectiveness of the graft copolymers for the removal of two standard dyes, malachite green and methyl green, was investigated. The prepared PAA-g-CMC adsorbents resulted in more than 80% of dye removal for malachite green and methyl green, displaying its great capacity to be utilized as an alternative material for wastewater treatment.

        Speaker: Ms. Pattra Lertsarawut (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Effect of Gamma Irradiation on Lipid Peroxidation and Plant Development of Turmeric $\textit{in vitro}$ Culture 1h

        Gamma radiation has been widely applied in agriculture for crop improvement, however, it can induce oxidative stress in plants cell. This research aims to study effects of acute and chronic gamma irradiation on lipid peroxidation and plant development in M1V1 generation of turmeric. Plantlets cultured on MS medium were exposed to acute gamma radiation from Cs-137 (dose rate 3.7 Gy/min) at 0, 20, 40, 60 and 80 Gy. For chronic irradiation with a Co-60 source (dose rate 0.0057 Gy/min), turmeric were exposed to gamma radiation at 0, 21, 41, 62 and 82 Gy. Results showed that the content of malondialdehyde (MDA) gradually increased with radiation doses after chronic irradiation, whereas after acute irradiation, it significantly increased at the dose of 40 Gy compared to non-irradiated plantlets. Differences between acute and chronical exposure to gamma irradiation were observed for MDA at the highest dose. Chronic irradiation at 21, 41 and 62 Gy also influenced plant development, mainly due to stimulated seedling survival and growth, while 20 Gy acutely gamma irradiation maximally promoted and decreased afterward. The chlorophyll deficiency in the form of variegated leaf and light green leaf were observed in irradiated plantlets.

        Speaker: Dr. Katarut Chusree_aeom (Department of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University)
      • 14:50
        Effect of the Gamma Radiation Dose Rate and the High Voltage Supply from Battery for Survey Meter Calibration. 1h

        The radiation survey meter is a necessary equipment for the radiation operator to determine the quantities of the ambient dose equivalent, H*(d) in the radiation workplace. In order to preserve the reliability and performance, those instruments should be maintained and calibrated periodically. There are many commercial brands of radiological survey meters and dosimetry devices that are operating using battery. Therefore, the direct current (DC) voltage supply for each instrument is very important parameter which may affect to the accuracy and precision of the radiation measurement.
        This research aims to study the effect of the DC voltage supply variation to the generation of high voltage (HV) supply and measured radiation dose rate of the Geiger-muller counter (GM) type survey meters. In order to decide the appropriate DC voltage level for each model of the survey meters, the survey meter would be calibrated on the $^{137}$Cs gamma ray radiation field and measured radiation dose rate by varied DC voltage from maximum allowance downward until the HV indicator is lower than manufacturer recommended. Three models of GM type survey meters: model 5 (manufacturer by Ludlum Measurements, Inc.), model ND-2000 (manufacturer by NDS Products Inc.) and model 5701-I (manufacturer by Thailand Institute of Nuclear Technology (TINT)) were engaged in this study. The results of this study will be discussed.

        Keywords: calibration, survey meter, direct current (DC) voltage supply, high voltage supply

        Speaker: Mr. Thiti Rungseesumran (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Effect of Zinc Oxide on Elastic and Structural Properties of Recycled Window Glass: A Comparative Study Between Before and After Gamma Ray Irradiation on Glass Samples 1h

        A comparative study between before and after gamma ray irradiation on elastic and structural properties for (90-x)RWG – 10Na$_2$O – xZnO glass systems where RWG is recycled window glass and x is 0, 0.001, 0.01, 0.1, and 1.0 mol%, was carried out. The glass samples were prepared by melt quenching method at 1250 ℃. Densities of the prepared glass were measured based on Archimedes’ principle with n-hexane as immersion liquid. The glass samples were irradiated to doses 1 kGy of gamma irradiation at room temperature. The elastic and structural properties were evaluated by measuring the ultrasonic wave velocities both before and after gamma ray irradiation. Moreover, FTIR spectra were measured to investigate the effects of irradiation on the structure of the prepared glass. The results confirmed NBOs forming in the network structures of the glass samples after gamma ray irradiation, also supported the change of elastic moduli. In addition, radiation shielding properties were accompanied by theoretical computation of $\mu_\text{m}$ and HVL in the wide photon energy range varying from 1 keV to 100 GeV by WinXCom program, and compared with standard radiation shielding concretes.

        Keyword: Recycled window glass, Elastic moduli, Gamma ray irradiation, Radiation shielding glass

        Speaker: Poonnaphob Sopapan (Department of Physics, Faculty of Science, Ubon Ratchathani University)
      • 14:50
        Effects of Eggshell Powders on Mechanical and Electrical Properties of Gamma Vulcanized Natural Rubber Latex 1h

        Eggshell powders (ESP), which contain high percentage of CaCO$_3$, could be used as an effective and environmental-friendly bio-filler in gamma vulcanized natural rubber latex (GVNRL) in order to improve overall mechanical and electrical resistivity properties of the composites. This work investigated effects of adding ESP to GVNRL composites by measuring tensile properties, hardness (Shore A), volume resistivity, morphology, and infrared (IR) spectrum of the samples with the gamma irradiation doses varied from 0 to 30 kGy in 10-kGy increments and the contents of ESP varied from 0 to 6 parts per hundred parts of rubber by weight (phr) in 2-phr increments. The results showed that tensile modulus at 500% elongation, tensile strength, hardness (Shore A), and volume resistivity increased, while elongation at break decreased with increasing ESP contents. In terms of effects of gamma irradiation doses, the results showed that tensile modulus at 500% elongation and hardness (Shore A) increased, while elongation at break decreased with increasing gamma irradiation doses. However, tensile strength behaved differently, initially increased and became relatively constant after 10 kGy of gamma doses. In conclusions, adding ESP to GVNRL composites improved overall mechanical and electrical resistivity properties of the composites by acting as an effecting reinforcing filler of the composites. Hence, ESP could be used as an alternative source of CaCO$_3$ in rubber industries in lieu of a traditional CaCO$_3$ that is commonly produced from limestone.
        Keywords: Eggshell, natural rubber latex, gamma vulcanization, tensile properties, volume resistivity, FT-IR

        Speaker: Ms. Budsaraphorn Moonlek (Department of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University)
      • 14:50
        Effects of Gamma Irradiation on Antioxidant Activities and Chemical Properties in $\textit{Agaricus bisporus}$ Mushrooms 1h

        $\textit{Agaricus bisporus}$ is easily perishable and subject to microbial contamination. The present study aspires to follow antioxidant activities and chemical changes of $\textit{Agaricus bisporus}$ after being exposed to gamma radiation. Powder samples were irradiated at 2.5, 5, 7.5 and 10 kGy. Subsequently, antioxidant activities, total protein content and total soluble polysaccharide content of irradiated samples were evaluated. Result showed that gamma irradiation up to 10 kGy did not significantly affect antioxidant activities. 1,1-diphenyl-2-picrylhydrazyl radical (DPPH) value of non-irradiated and irradiated samples ranged from 2.07 ± 0.09 to 2.19 ± 0.14 mgAAE/g, whereas ferric ion reducing antioxidant power (FRAP) of irradiated samples varied from 32.74 ± 0.39 to 34.52 ± 1.45 μmolFeSO$_4$/g. Total phenolic contents were between 7.24 ± 0.38 and 7.65 ± 0.53 mgGAE/g. In terms of chemical properties, gamma radiation at 10 kGy showed no significant differences in total protein content and total water soluble polysaccharide content. Total protein contents were found from 42.46 ± 0.28 to 43.18 ± 0.13 %w/w. Amount of total water soluble polysaccharide content in non-irradiated and irradiated samples varied from 5.49 ± 0.15 to 5.72 ± 0.14 %w/w.

        Speaker: Ms. Wachiraporn Pewlong (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Effects of Gamma Irradiation on Antioxidant Properties and Microbial Contamination in $\textit{Boletus griseipureus}$ Corner. 1h

        The aim of this research is to investigate effects of gamma irradiation on antioxidant properties and microbial contaminants in Boletus griseipureus. Samples were ground into powder and later subject to gamma irradiation at 2.5, 5, 7.5 and 10 kGy. The non-irradiated and irradiated samples were then analyzed for their microbial contamination and antioxidant properties such as 2,2-diphenyl-1-picrylhydrazyl (DPPH) radical scavenging, ferric reducing antioxidant power (FRAP), total phenolic content, beta glucan content and total triterpenoids. Results showed that microbial contamination decreased with increasing dose. In terms of antioxidant properties, gamma irradiation did not result in significant effects on FRAP, total phenolic content, beta glucan content, and total triterpenoids. However, at 10 kGy of gamma irradiation, DPPH radical scavenging notably increased (p < 0.05).

        Speaker: Ms. Sirilak Chookaew (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Effects of Irradiation on Antioxidant and Antimicrobial Activities of $\textit{Coscinium fenestratum}$ (Goetgh.) Colebr. 1h

        This study aims to investigate effects of gamma radiation on antimicrobial activities (against Staphylococcus aureus and Escherichia coli) and antioxidant activities of Coscinium fenestratum (Goetgh.) Colebr., known in Thai as Haem herb. Gamma irradiation was applied to powder samples of Haem herb at 5, 10, 15 and 20 kGy. The 60% ethanolic extracts of irradiated and non-irradiated samples were prepared to evaluate total phenolic contents (TPC), antioxidant and antimicrobial activities. Results indicated that TPC of irradiated and non-irradiated samples was not significantly different (p<0.05), ranging from 11.39 ± 1.17 to 11.99 ± 1.10 mgGAE/g. Ferric reducing antioxidant potential and 1,1-diphenyl-2-picrylhydrazyl radical scavenging activity significantly increased (p<0.05) after gamma irradiation at 20 kGy and 5 kGy, respectively. The antimicrobial activity was done using agar disc diffusion method. Results revealed that 60% ethanolic extracts of various samples exhibited antibacterial activity against Staphylococcus aureus with range of inhibition zone 16.3 – 17.5 mm.

        Speaker: Ms. Jaruratana Eamsiri (Thailand Institue of Nuclear Technology (Plubic Organization))
      • 14:50
        Evolution of Rare Earth Elements, Uranium and Thorium in Geological Samples by ICP-OES and Their Characterization 1h

        Inductively coupled plasma optical emission spectrometry (ICP-OES) was used to determine rare earth elements, uranium and thorium in granitic soils and rock samples collected from Chumporn and Surat Thani provinces, the southern part of Thailand. The effect of digestion temperature (125$^{\circ}$C, 160$^{\circ}$C, 200$^{\circ}$C and 240$^{\circ}$C) on the concentration levels of elements was investigated. It was found that the digestion temperature of 160$^{\circ}$C could efficiently leach out the elements to achieve the high concentration of elements for soil samples at different horizons such as O-A, A-B, B-C (1) and B-C(2). For rock sample (D horizon), the digestion temperature did not significantly affect extraction of the elements. The results of the analytical study were also compared with the results determined by ICP-MS/OES as obtained from Department of Mineral Resources, Thailand (DMR). A good correlation between the determined values digested at 160 oC and the values measured by ICP-MS/OES as obtained from DMR were found for Ce, La, Pr, Nd, Y, Dy, Eu and Th. The SEM-EDS results demonstrated that the samples particles mainly consisted of Si, and Al with varying amount of Fe, K, Mg, Ca, Na and Ti. Quartz and albite were found to exist in all samples that were confirmed by XRD analysis.

        Speaker: Dr. Dussadee Rattanaphra (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Evolution of the Toroidal Rotation and the Radial Electric Field during Pellet Injection in ITER and DEMOs 1h

        The toroidal rotation model based on the intrinsic torque from Neoclassical Toroidal Viscosity (NTV) theory is implemented in TASK/TR code and used together with a combination of a gyro-Landau-fluid (GLF) transport model and NCLASS neoclassical transport model to predict the evolution of plasma profiles and, consequently, the fusion performance during the injection of high-field-sided (HFS) pellets in ITER and two proposed designs of Demonstration Fusion Power Plant (DEMO): European and Indian designs. The pellet ablation in plasma is described using the neutral gas shielding (NGS) model with the magnetic gradient drift effects included. It is found that, during pellet operation in all three machines, the toroidal velocity in the region of the peaked density induced by pellet significantly decreases depending on the strength of pellets. From a radial force balance analysis, such toroidal velocity directly and strongly affects the behaviour of radial electric field in that region. This is caused by a reduction of toroidal velocity component, where the other components remain almost the same. It is also found that when the density is increased due to pellet injection, the bootstrap current, plasma stored energy, and alpha power are increased depending sensitively on the pellet frequency and radius.

        Speaker: Apiwat Wisitsorasak (King Mongkut's University of Technology Thonburi)
      • 14:50
        Feasibility Study of Neutron Production at SLRI Beam Test Facility 1h

        SLRI Beam Test Facility (SLRI-BTF) has been constructed in order to increase usage of the Siam Photon Source injector. SLRI-BTF aims to provide electron test beams for calibration and testing of high-energy particle detectors and diagnostic instrumentations. The test-beam energy varies from 40 MeV to 1.2 GeV with adjustable intensity from a few to several millions of electrons per repetition rate. Since the test-beam energy is sufficiently large, the electron test beam can be used to produce photo-neutrons resulted from collision of high-energy electrons to metal targets. Similar to the electron test beams, this neutron source will be utilized for calibration and testing of neutron detectors and instrumentations. In this work, the neutron production and its angular dependence has been investigated using simulation. The result based on this study will be used to determine the possibility to service neutron source for user in the future.

        Speaker: Dr. Kritsada Kittimanapun (Synchrotron Light Research Institute)
      • 14:50
        Geographical Origin of Thai Hom Mali Rice based on Elemental and Stable Isotopic Compositions 1h

        Thai Hom Mali rice is an economic crop of Thailand and well-known as a premium rice in the world trade. In this research, Thai Hom Mali rice samples were collected from the paddy fields in the northern and northeastern regions of Thailand for verifying the authenticity of rice origin. Multi-element and stable isotopic compositions in rice samples were determined by inductively coupled plasma mass spectrometry (ICP-MS) and isotope ratio mass spectrometry (IRMS), respectively. A radar plot was applied to discriminate the origin of rice. Thai Hom Mali Rice from both regions had similar pattern of isotopic composition. The two regions clearly displayed different distribution of elemental patterns. Therefore, Thai Hom Mali rice can be differentiated from each region using multi-element combined with a radar plot.

        Speaker: Ms. Wannee Srinuttrakul (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Green and Environmental-Friendly Synthesis of Reduced Graphene Oxide (rGO) Using Gamma Irradiation 1h

        Graphene is known to be one of the strongest materials with excellent heat and electricity conductivity that can be used in various applications including solar cells, LED production, and electrical devices. This work aimed to investigate on possible green and environmental-friendly synthesis of reduced graphene oxide (rGO) that can be used as a basis for graphene production using gamma irradiation with the doses varied from 0 to 42 kGy in 7-kGy increments. Analytical techniques used in the characterization of the synthesized rGO included the Scanning Electron Microscopy (SEM) with Energy Dispersive Spectroscopy (EDS), and UV-Vis spectroscopy. The results showed that irradiated graphene oxide (GO) with gamma rays caused the surface of GO to have more wrinkles and crumples due to the formation and reconstruction of new chemical bonds on the single layered carbon, while spectrums from UV-Vis spectroscopy revealed the disappearance of the absorption peak at 292 nm, which indicated n→π* transitions of C=O, after gamma irradiation. Furthermore, results from EDS showed that the ratios of C:O of graphene oxide increased from 49:51 to 69:31 by atomic weight or from 56:44 to 75:25 by atomic contents, after gamma irradiation at 35 kGy. The increases in these reported ratios implied the reduction of oxygen and the production of rGO using gamma irradiation. As a result, gamma irradiation on GO can successfully produce rGO that can be used in graphene production that are much safer and more environment-friendly than using chemical or electrochemical techniques.

        Speaker: Ms. Pinyapach Tiamduangtawan (Department of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University)
      • 14:50
        Induction of Gamma Irradiation for Microorganism Decontamination on Dried Lotus Pollen ($\textit{Nelumbo nucifera}$) 1h

        Gamma irradiation is well known as a safe method for food decontamination, due to its great effect for inactivating microorganisms in various foods. In this study, effects of gamma radiation on microbial load and antioxidant properties of dried lotus pollen were investigated. Samples were subject to gamma irradiation at 5 and 10 kGy. Results showed that initial load of total plate count (TPC) and total yeast and mold (TYM) were $1.9 \times 10^5$ and $2.3 \times 10^3$ CFU/g, respectively. After irradiation at 5 kGy, TPC and TYM decreased to $5.5 \times 10^3$ and 13 CFU/g, respectively, whereas after irradiation at 10 kGy, TPC and TYM diminished to 60 and < 10 CFU/g, in that order. As for antioxidant properties, non-irradiated and irradiated samples displayed no significant differences. These results proved that gamma irradiation at 5 kGy can be used as a method with great potential for microbial load decontamination to improve hygienic quality of dried lotus pollen.

        Speaker: Mr. Surasak Sajjabut (Thailand Institute of Nuclear Technology)
      • 14:50
        Influence of Gamma Ray Irradiation on Elastic and Structural Properties of Recycled Window Glass Doped with Chromium Oxide by Using Ultrasonic Contact Technique and FTIR Spectroscopy 1h

        Glasses of system 90RWG – 10Na$_2$O – x Cr$_2$O$_3$ (RWG stands for recycled window glass and x = 0.001, 0.01, 0.1, 1 mol %) have been prepared by the melt-quenching method. The Archimedes principle was used to measure density of the glass samples, and then these data were used to calculate the molar volumes. Ultrasonic velocities were measured by using the ultrasonic contact technique at 4 MHz frequency and at room temperature. Elastic moduli, Poisson's ratio and micro-hardness have been calculated. The obtained results were compared with theoretical values which were calculated from the Makishima-Mackenzie model. The glass samples were gamma irradiated using a $^{60}$Co gamma cell at the total gamma dose 1000 Gy. Then the effects of gamma ray irradiation on structure properties of the glasses were investigated by means of their elastic moduli. FTIR spectra were also recorded to support the result from ultrasonic contact technique. The results show that there are significant changes of NBO that increasing and decreasing in the structural glass due to the difference of the chromium oxide adding and the effect of gamma irradiation.

        Keywords: Glass, Ultrasonic contact technique, Elastic properties, FTIR spectroscopy

        Speaker: Ms. Pattaranipa Gunhakoon (Ubon RatchathaniI University)
      • 14:50
        Investigation of the Protection Efficacy of Thai Medicinal Plants on Irradiation-Induced Plasmid DNA Damage 1h

        Extracts of Thai medicinal plants have been reported to be natural sources of antioxidants which can inhibit free radicals and have potential for radiation protection. In this study, we investigated the efficacy of five medicinal plant extracts, cinnamon, ginger, white kwao krua, black pepper, and moringa compared to gallic acid, which served as a positive control in the protection of plasmid pET-15b DNA after exposure to gamma irradiation. pET-15b plasmid DNA was irradiated by gamma radiation at 100 Gy with various concentrations of medicinal plant extracts and DNA damage was measured by using gel electrophoresis. The results showed that exposure of pET-15b plasmid DNA to 100 Gy of gamma radiation induced DNA strand breakage and plasmid DNA alteration from a supercoiled to open circular form. Extracts of moringa, cinnamon and ginger significantly reduced plasmid DNA damage by gamma radiation. While black pepper and white kwao krua extracts did not show observable radioprotective effects. The presence of moringa, cinnamon and ginger extracts during irradiation can protect pET-15b plasmid against radiation-induced DNA damage.

        Speaker: Ms. Piyanuch Orpong (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Major Element Analysis and Characterization of Geological Samples from Phuket Province, Thailand 1h

        This study focused on major element analysis of the geological samples by portable x-ray fluorescence spectrometer (pXRF) and the characterization of those samples by x-ray diffractometer (XRD) and scanning electron microscopy with energy dispersive x-ray spectroscopy (SEM/EDX). Ten samples from Phuket province, Thailand were collected with different depths corresponding to O horizon (0-0.3 m), A horizon (0.3-1 m), B1 horizon (1-2 m), B2 horizon (2-3 m), C1 horizon (3-5 m)), C2A horizon (0.3-8 m), C2B horizon (1-8 m), C3 horizon (8-12 m), D horizon (12-20 m) and RK horizon (> 20 m). Seven geological reference materials were used to calibrate the analytical method of pXRF. The elemental analysis results showed that the concentration values of each major element found in the different depths were not significantly different. The obtained concentrations range were Si (26-30 wt%), Al (13-18 wt%), Fe (2-4 wt%), K (2-5 wt%), Ti (0.2-0.4 wt%), Mg (0.1-0.4 wt%) and Ca (0.02-0.23 wt%). Some elements such as Ca and Mg could not be detected. The XRD patterns revealed that all samples consisted of quartz, kaolinite, microcline, halloysite, bentonite and montmorillonite. The SEM/EDX results were matched well with that pXRF results.

        Speaker: Sasikarn Nuchdang (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Method Validation of Tritium Measurement in Urine Sample 1h

        Method validation is a key part for radionuclide measurement in biological sample. To confirm that the method used is suitable for the application, this study was designed to validate a H$^{3}$ determination in urine sample using liquid scintillation counting technique. Urine samples obtained from PROCORAD were prepared by mixing 1 ml of urine, 10 ml of Ultima gold cocktail and 4 ml of water; kept in dark for 48 hr and measured for 45 min by Liquid scintillation counter PerkinElmer Tri-Carb 2910 TR. According to the measurement, counting efficiency was determined from quench correction equation. The measurement method was validated by critical limit of detection, minimal detection activity and the recovery percentage of H$^{3}$ in spiked sample. It was found that critical limit of detection and minimal detection activity were 6.47 CPM and 0.96 BqL$^{-1}$ respectively. The recovery of H$^{3}$ spiked sample was in a range of 107.09-111.49% (85-115%: acceptable level). Statistic analysis showed that Z-score is also in a range of 0.03-0.1 (less than 2: satisfactory result). Therefore, this method is suitable for the determination of H$^{3}$ in urine sample.

        Keywords: Tritium, Method Validation, Liquid scintillation counter

        Speaker: Mrs. Sujittra Phetwiset (Office of Atoms for Peace, 16 Vibhavadi-rangsit road, Ladyao, Chatuchak, Bangkok, THAILAND)
      • 14:50
        Monte Carlo Simulation for Cross-section Inspection of Chimney Tray Structure Inside the Distillation Column Based on Gamma Ray Computed Tomographic Method 1h

        This paper proposes the preliminary study of inspection method which can be applied to the internal structure inspection of distillation column in petroleum and petrochemical plants. The study was done through simulation using Monte Carlo for N-Particle (MCNP) Transport Computer Code to simulate the gamma ray transmission for Computed Tomography (CT) algorithm. The simulation results were used in back projection process to obtain the image in two dimensions (2D) using Filtered Back Projection algorithm (FBP). Gaseous riser pipes array structure was selected as an interesting internal structure to be inspected since there were possibilities that one or more pipes might be damaged during operation. Three studied cases were defined to determine the resolution different by varied number of radiation detectors 21, 23 and 33 detectors, respectively. The last studied case was done to determine the detect-ability of this method if one pipe is missing from its place. Moreover, comparison of back projected image of 21 and 33 detectors was done. The results showed that reconstructed image resolution of image depended on number of detectors. Though smaller number of detectors was a poorer reconstructed image resolution, reconstructed image still provided a clue to inspector and induce the justification of problem location when one pipe was missing.

        Speaker: Mr. Dhanaj Saengchantr (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Natural Radioactivity Concentration in Traditional Thai Herbal Medicine 1h

        The aim of this study is to create a database of radioactivity concentration and annual effective dose of the naturally occurring radionuclides: $^{226}$Ra, $^{228}$Ra, $^{40}$K and $^{210}$Po in Thai medicinal herb plants. 99 types of popular Thai medicinal herb plants (total of 212 samples) such as $\textit{Curcuma comosa}$ Roxb., mucuna, white kwao krua, barbed grass, black galingale, lingzhi mushroom, $\textit{Ginkgo biloba}$, jiaogulan, plu kaow, turmeric, ginger, safflower, moringa, gotu kola and garlic were randomly collected from drug stores and herbal fair. The activity concentration of $^{226}$Ra, $^{228}$Ra and $^{40}$K in all herb samples was determined by gamma-ray spectrometry while that of $^{210}$Po was determined by alpha spectrometry. The activity concentration was found to range from <0.20 to 89.92 Bq kg$^{-1}$ for $^{226}$Ra, from <0.10 to 39.62 Bq kg$^{-1}$ for $^{228}$Ra and from 4.83 to 2761.33 Bq kg$^{-1}$ for $^{40}$K and from 0.32 to 47.13 Bq kg$^{-1}$ for $^{210}$Po. The highest activities concentration of $^{226}$Ra, $^{228}$Ra, $^{40}$K and $^{210}$Po were found in the white kwao krua, jiaogulan, plu kaow and ginkgo, respectively. The average total annual effective dose due to ingestion of these herbal plants was assessed to range from 0.0001 to 0.0327 mSv y$^{-1}$, with highest dose found in jiaogulan.

        Speaker: Dr. Chutima Kranrod (Chulalongkorn University)
      • 14:50
        Numerical Tracking of Impurities by Dust Ablation in HT-6M plasma 1h

        Thailand Institute of Nuclear Technology (TINT) plan to operate the refurbished HT-6M tokamak near 2020. Although, the tokamak is old, small and low in power, it is still useful for the plasma and fusion education. With regards to researching, there are still rooms for frontier researches crucial for efficient fusion operations. One of them is the phenomena related to dust and droplet transport. In this work, we aim to track various dust during transport under the plasma profiles of the HT-6M. The plasma profiles are generated by the TASK code. The simulation of dust is conducted by the Dust and Droplet Tracking (DDT) code. Various dust parameters including selected notable dust materials e.g. carbon, boron, lithium etc. are implemented in the simulation to learn their behaviors for HT-6M. The aim for the work is to support on the preparation of the HT-6M installation. This is because the knowledge gained from experiments and diagnostics on dust and droplet transport should contribute to the improvement of fusion operations in terms of, such as impurity transport, implementation of liquid metal (lithium/tin) for inner-wall, radiation cooling, pellet transport etc. Those experiments seems to be achievable by the ability of the refurbished HT-6M.

        Speaker: Dr. Nopparit Somboonkittichai (Department of Physics, Faculty of Science, Kasetsart University)
      • 14:50
        Power Supply System for Dielectric Barrier Discharge Plasma Parallel Plate Reactor 1h

        A power supply system for dielectric barrier discharge plasma torch was constructed, which can supply high voltage up to 15 kV and current up to 100 mA with an adjustable frequency in the range 20 – 20,000 Hz. The system consisted of a signal generator, a signal amplifier, a step-up transformer and several neon sign transformers connected in parallel. The system was utilized to generate atmospheric plasma to assist the transesterification reaction. The vegetable oil:methanol molar ratio was 6:1. The vegetable oil volume was 100 ml. The reaction was performed at room temperature and 60°C. A peristaltic pump was used for circulation. The cathode-anode distance was 3 mm. An atomizing nozzle was used to spray the oil-methanol mixture and the reaction time was 2 hours. It was found that the biodiesel yield was less than 1% for both temperatures and that no glycerol was present in the system. This is because when the oil-methanol mixture was in contact with the parallel plates, it behaved as an insulator, resulting in reduction of plasma generation and reduced reaction. However, it was shown that the constructed power supply system was able to successfully generate plasma.

        Speaker: Ms. Kunlanan Puprasit (Chulalongkorn University)
      • 14:50
        Prediction of Tritium Production Flux from a Modeled Tokamak Blanket Using Monte Carlo Code 1h

        The production of tritium from a lithium blanket with a vanadium alloy structure was predicted using the MCNP. The model was designed to include a lithium breeder, reflector, shielding and structure. Different forms of lithium, including natural lithium, FLiBe and LiPb, were considered. LiPb had the highest tritium production per source neutron among the three forms of lithium considered. In addition, it was found that the concentration of $^6$Li in the liquid lithium strongly affected tritium production from the model blanket. With 75 percent $^6$Li enrichment in the LiPb, the overall tritium production in the breeder zone was about 8 particle/cm$^2$/source neutron, which was more than two times of that using natural lithium. Moreover, the tritium production rate reduced up to 15% when the 2-cm thick of tungsten was added in front of the breeding zone as a first wall material.

        Speaker: Dr. Siriyaporn Sangaroon (Department of Physics, Faculty of Science, Mahasarakham University)
      • 14:50
        Preliminary Study of Neutron Tomography Performance Using a Standard Specimen 1h

        In the past few years, neutron tomography in Thailand was recently established at Thai Research Reactor TRR-1/M1, Thailand Institute of Nuclear Technology (Public Organization) for research and service, as the technique is useful for non-destructive internal structure investigation. During the establishment phase, many types of specimens were tested. In this work, a standard specimen was used to test the performance of the neutron tomography setup. The specimen, namely test strip B is a standard object for neutron radiography from Argonne National Laboratory, USA. It is made of thin cadmium plate drilled with different hole sizes, contains plastic wires and cadmium wires with different diameters. A compact neutron tomography system, consisting of an L-shaped box, with a LiF/ZnS scintillation screen and a CCD camera, and an in-house developed rotation stage, was used to conduct the experiment. The preliminary study was conducted with 30 sec-exposure time per step, 1.8 degree angular step with the total of 100 neutron projections. The 3D neutron tomography was reconstructed with Octopus Imaging software. The recorded images are shown and discussed in this work. The aim of this research is to evaluate neutron tomography performance, especially resolution, using a standard specimen in order to potentially improve the facility for non-destructive testing service and international research collaboration.

        Speaker: Mr. Weerawat Pornroongruengchok (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        Simulation Study of Plasma Boundary in Thailand Future Tokamak using Two-Points Model 1h

        As Thailand has been preparing to operate a small tokamak in which the device will be upgraded from HT-6M tokamak, the quantitative information about the plasma in the edge and at the material surface would be insightful for future experimental operations. In this work, we use a simple two-point model to investigate the particle and heat exhausted from the core to the limiter for the tokamak with nominal parameters of HT-6M. The model assumes that the transports of heat and particle from the core enter the scrape-off layer at the outer midplane. They then travel to the limiter along the magnetic field line. In this scrape-off layer region, the parallel transport dominates the cross-field transport. Thus the transport equations can be reduced to a set of nonlinear equations that relates the density and temperature at the upstream to those at the limiter. It is found that the electron temperature at the limiter surface is in the range of 1-100 eV depending on the particle and heat fluxes from the core. Furthermore the conditions for the plasma detachment are also explored.

        Speaker: Rungsin Kongkerd (Department of Physics ,King Monkut's University of Technology Thonburi)
      • 14:50
        The Evaluation of Measurement Uncertainty for Personal Dosimetry Using NanoDot Optically Stimulated Luminescence Dosimeter (OSLD) 1h

        The aim of this research is to evaluate the measurement uncertainty for personal dosimetry using NanoDot Optically Stimulated Luminescence (OSL) of the Office of Atoms for Peace (OAP). The nanoDot dosimeter which uses for medical dosimeter was selected and irradiated of absorbed dose in free air at 5 mSv of Cs-137 at Secondary Standard Dosimetry Laboratory of OAP. The measurement uncertainty was combined from inhomogeneity of detector sensitivity, variability of detector reading due to limited sensitivity and background, variability of detector reading at zero dose, energy and direction dependence, non-linearity of response, fading, dependence ambient temperature and humidity and variation in local natural background, effects of light, calibration error, correction error for reading algorithm and performance test following IEC TR 62461 and IAEA 99. The result of combination uncertainty is 3.725 ± 1.246 mGy at 95% confidence. For the linearity performance test, the absorbed dose above 4 mGy was passed the criteria when following IEC TR 62461 standard. However, when the IAEA 99 standard was used, the absorbed dose above 1 mGy was passed the criteria.

        Speaker: Mr. Pongphanot Rindhatayathon (Office of Atoms for Peace)
      • 14:50
        The Impact of Electron Beam Irradiation in Topaz Quality Enhancement 1h

        Electron beam irradiation was applied on the quality enhancement of topaz originated from Yen Bai province in northern Vietnam. The process of enhancement was carefully taken by consideration on the optimization of power and energy of electron, efficient cooling system, annealing process and radioactivity occurring and remaining. The two of topaz sample were irradiated by 20 MeV electron beam with different fluences of $1.34 \times 10^{16}$ cm$^{-2}$ and $2.64 \times 10^{16}$ cm$^{-2}$, respectively. Then the irradiated sample was individually investigated by UV–Vis, EPR, FTIR and WD-XRF spectroscopy. The characteristic spectra obtained from the investigation compared to the natural topaz sample afterwards. Interaction of radiation with impurity ions in topaz sample during irradiation resulted in changing of colorless to sky blue topaz, which had the broad absorption band of UV-Vis spectroscopy at 620 nm. The EPR spectrum of topaz sample showing a single broad isotropic line with g = 2.012 that are correlated with an O-center in the topaz structure. FTIR spectra indicated that sky blue color may originate from the decomposition of hydroxyl group (OH) by the electron beam irradiation.

        Speaker: Dr. Apichate Maneewong (Irradiation Center, Thailand Institute of Nuclear Technology (Public Organization))
      • 14:50
        The Implementation of Malaysian Skills Certification Scheme for Non-Destructive Testing (NDT) Personnel 1h

        The Department of Skills Development (DSD) is a government agency who is responsible for formulating, promoting and coordinating strategies and skills training program in Malaysia. Without exception the DSD has been the national certification of the Non-Destructive Testing (NDT) personnel since 1986 and has been accredited with ISO / IEC17024 for the scope of NDT since 2012. The training and certification scheme provided complies with international standard ISO 9712 as a means to ascertain international recognition and preparing NDT personnel to perform inspection on engineering materials, components and structures in a reliable manner. National Occupational Skills Standard (NOSS) is made available as a basis for training, examination and certification. DSD has established a systematic certification scheme including occupational standard, accreditation criteria and procedures as well as examination and quality assurance system in order to comply with ISO 9712 requirements. Under this scheme, DSD certifies a competent candidate with Malaysian Skills Certificates Level 1 to Level 3 for various NDT method including Radiographic Testing (RT), Eddy Current Testing (ET), Liquid Penetrant Testing (PT), Magnetic Particle Testing (MT), Radiography Interpreter (RI) and Digital Industrial Radiography (DIR). This paper aims to provide an overview of how DSD operates Malaysian Skills Certification Scheme for NDT personnel.

        Speakers: Dr. Alina A Rahman (Department of Skills Development, Ministry of Human Resources, Malaysia), Mr. Mohd Hafiz Hassan (Department of Skills Development, Ministry of Human Resources, Malaysia)
      • 14:50
        Verification of $^{90}$Sr determination in marine animals 1h

        Sr-90 is considered as a hazardous radiounclide for humans. When it is consumed, it would be eventually accumulated in bone and its daughter, $^{90}$Y, could then harm bone marrow. To monitor $^{90}$Sr in the environment especially in marine food samples it is very important for Thailand as the consumtion of marine animals is high and these animals are also exported all over the world and play an important part of the economy. To measure $^{90}$Sr in our food samples, a liquid extraction technique using bis-2-etylhexyl-phosphoric acid to separate and purify yttrium followed by Cherenkov counting to determine $^{90}$Y in secular equilibrium to $^{90}$Sr were developed at the Office of Atoms for Peace’s laboratory. The analytical performance was validated for all criteria i.e. accuracy, precision and trueness. Sr-90 determination in spiked mussel samples with various activity concentrations in a range of 2 – 1000 Bq/kg dry weight were performed for statistical evaluation. The results had a relative bias within the accepted relative bias of +/-25% i.e. in the range from 10.36 to 16.98 and passed all criteria. This could confirm our analytical approach for $^{90}$Sr determination in marine animals and foodstuffs was accepted. Moreover the method is cost-efficient, simple and fast to analyse $^{90}$Sr in the samples.

        Speaker: Dr. Suputtra Visetpotjanakit (Office of Atoms for Peace)
    • 15:50 17:00
      Oral 2: Block II
      • 15:50
        Plant Mutation Breeding and Bio Techniques for Crop Improvement 30m

        Modern plant breeding is classified into three types of breeding; conventional, mutation and transgenic. In one way, mutation breeding serves as a global focal point for nuclear cooperation, mobilizing peaceful applications of nuclear science and technology for critical needs in developing countries, including Thailand. The main objective of mutation breeding in Thailand is to identify high yielding food crop germplasm that can contribute to sustainable food security with a major focus on cereals (rice, grain legume), vegetables (water melon, chili) and ornamental (orchid, chrysanthemum). Plant mutation breeding requires genetic variation which is a source of evolution. Mutation induction creates a new variant that is different from the parent and the induced mutants are not GMOs, as there is no introduction of foreign hereditary material into induced mutant germplasm. Examples of key objectives of mutation in Thailand are to develop and characterize abiotic and biotic tolerant mutant germplasm and to breed disease resistant as new varieties with increased biotic tolerance. Plant breeding and genetic procedures usually start with mutation induction by irradiation or chemical mutagen and subsequently join force with other techniques such as tissue culture or molecular genetics.

        Speaker: Vichai Puripunyavanich (Thailand Institute of Nuclear Technology)
      • 16:20
        Neutron Activation Analysis for APDC/MIBK Extractable Inorganic Arsenic (III) and Arsenic (V) Species in Japanese Hijiki 20m

        Japanese hijiki, one of the most common edible seaweeds, is known to contain both AS(III) and AS(V) in inorganic forms as well as bound to organic molecules. It is of interest to develop methods for the determination of total and inorganic arsenic species in hijiki. In this work, raw and cooked hijiki samples were analyzed by instrumental neutron activation analysis (INAA). Samples were irradiated for 3 h at a neutron flux of $1\times10^{12}$ cm$^{−2}$ s$^{−1}$ at the Thailand Institute of Nuclear Technology (TINT) reactor facility. After 1-day decay time, the samples were counted using a HPGE detector gamma-ray spectrometry system. To validate the INAA method arsenic levels were measured in three certified reference materials. Levels of inorganic As(III) and As(V) in the reference materials and hijiki samples were also measured by separating these species followed by NAA. The separation method consisted of solvent extraction by APDC/MIBK and back extraction of the species in to nitric acid. Details of the methods used and results obtained will be presented.

        Speaker: Dr. Michiko Fukushima (Ishinomaki Senshu University)
      • 16:40
        Development of Radiation Imaging System for Nutrient Distribution in Sapling 20m

        Radioactive tracer in plant commonly uses X-ray films or imaging plate for study nutrient distribution, which cause radioactive waste. We developed a real-time imaging system for radiotracer in sapling to reduced samples and radioactive waste. The main components of the developed system consist of the radiation detector, mechanical part, and the control software. We used 4x4 pixels of Silicon Photomultiplier (SiPM) model ArrayC-30035-16P from sensL coupling with 16 plastic scintillators as a radiation detector. The signals from the detector were amplified, collected number of pulses based on each pixel, and then transferred to the control software on a personal computer (PC) for constructed an image. The mechanical parts of the system were modified from MicromakeC1 3D printer which could control the movement of each motor in Y and X axes with customizing electronic circuit board communicated to the control software on PC via RS232. Furthermore, the control software that developed from LabVIEW program communicated with the developed detector to get pulse signals and also controlled the mechanical parts to scan over an area of a sample. The number of counts in each pixel from the scanning process was constructed and transformed into the grayscale image. The developed radiation imaging system from this research can use to measure a sample with maximum size at 300 x 300 mm with the precision of motors is 0.1 mm. The control software can adjust the counting time, pitch of motor, scanning area, and provide a grayscale image that shows the accumulation and distribution of radioisotope. Therefore the developed radiation imaging system can be applied to a process of radioactive tracer in the sapling.

        Speaker: Pathcharanan Tuanghirunwimol (Department of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University)
    • 09:00 10:40
      Oral 3: Block III
      • 09:00
        Modeling Rumor Spreading and Debunking Strategies on Social Media During Disasters 30m

        Increasingly, social media has been used as a platform for providing timely crisis communication during a disaster. Unfortunately, rumor spreading, and in particular, rumors that are later proven to be untrue, have been identified as critical issues for the use of social media during disasters. Few research has studied the users’ behavior when facing rumors and debunking information. In this research, we first study the effectiveness of crisis communication and how retweet and mention could help improve crisis information impression. Millions of tweets posted during Hurricanes Harvey, Irma, and Sandy are collected and analyzed. Second, we investigate several cases of rumor responding and debunking behaviors of Twitter users during Hurricane Sandy in 2012 and Boston Marathon bombings in 2013. We find that for users who were misinformed and reacted by posting tweet(s), they could respond to this rumor by: spreading (~86%), seeking confirmation (~9%), or doubting (~10%). Given rumor spreading users were debunked, they would respond by: deleting rumor tweets (~10%), clarifying rumor information with a new tweet (~19%), or doing nothing (~78%). Finally, we discuss the optimal debunking strategies dealing with potential rumor information, and the corresponding consequences on the downstream information sharing. We also use simulation to study the impact of different network information flow structure. This research provides some novel insights on crisis communication and rumor management using social media during disasters.

        Speaker: Jun Zhuang (University at Buffalo)
      • 09:30
        The New Instrumentation and Control System of the TRIGA Mark II Reactor Vienna 30m

        The TRIGA Mark II Reactor of the Atominstitut Vienna went critical for the first time at 7.3.1962. Within the framework of the “global threat reduction initiative (GTRI)”, all fuel elements (several of them high enriched) were shipped back to Idaho Falls, US in 2012. In return, slightly used and low enriched fuel elements were delivered from US to the Institute. Subsequently, between 2015 and 2017 the Instrumentation & Control System (I&C) and reactor related components including the primary, secondary and purification circuits (heat exchanger, ion exchanger), the ventilation system and other auxiliary systems (crane, cables, lightning, power supply (also UPS)) were replaced. In addition, the security system and radiation protection system were also renewed. The presentation will describe the renewal process including technical challenges.

        Speaker: Dr. Andreas Musilek (Technical University Vienna, Atominstitut)
      • 10:00
        Dose Assessment Using RESRAD and Input Values Applicable to Unit 1 of Kori Nuclear Power Plant in Korea 20m

        Unit 1 of Kori nuclear power plant, which had been operated for 40 years in Korea, was permanently shut down on June 2017. After its closing and decommissioning, it is important to determine its site-specific cleanup guidance levels. The most commonly used evaluation for determining the site release condition is RESRAD code developed by Argonne National Laboratory. But, the input values in RESRAD should be defined by applying the characteristics of site, exposure pathways and public members in Kori region. It is also important to determine the critical group by exposure scenario applicable to radiological assessment. Critical group was defined by reviewing three age groups of infant, child, and adult recommended in ICRP 101A. Determining critical group and its radiological assessment have been applied for resident farmer scenario understood to be conservative. Input values have been derived by reviewing FSAR of unit 1 of Kori nuclear power plant, population statistics, and national food and nutrition statistics. Critical group has been determined by calculating maximum dose by age group, the preference of foodstuff, metabolic characteristic and population distribution of Kori region, and is then to be 40~50 age. Doses have been evaluated by probabilistic approach by applying site-specific data, and sensitivity analysis is also performed. Uncertainty analysis is also performed and the representative quantities are finally determined for dose distribution of resident farmer scenario. It is summarized that critical group has been determined by applying site-specific data of Kori region, and so has dose assessment. From overall results, it is concluded that the optimized site release condition can be determined in decommissioning of nuclear facilities in Korea and the radiological protection for workers, public members and environment be improved.

        Speaker: Ms. Seung Hyun Lee (Korean Association for Radiation Application)
      • 10:20
        Investigation of Differences of Phenomena of Diffusiophoresis and Thermophoresis from Aerosol Deposition in Modified ART Mod 2 Code 20m

        Fission product behavior assessment in containment vessel is one of the important areas in safety assessments because the containment vessel is the final release protection. Modified ART Mod 2 code is used to study aerosol deposition phenomena in the containment vessel. From Phébus FPT experiments, there are occurrences of diffusiophoresis and thermophoresis on condensers in the containment vessel. These phenomena are recognized to be the same thing. However, this is not a universal view on these phenomena, and diffusiophoresis and thermophoresis are evaluated separately in the modified ART Mod 2 code. In previous study on the modified ART Mod 2 calculation of Phébus FPT experiments, there was more diffusiophoresis than thermophoresis in the case of single volume for containment vessel while there was more thermophoresis in the case of multiple volumes. This research aim is to conduct a sensitivity analysis of representative parameters affecting diffusiophoresis and thermophoresis namely pressure, aerosol size and temperature, under different nodalization in the modified ART Mod 2 code using Phébus FPT experiments to investigate differences. As a result, differences of temperature between atmosphere and wall in single volume affect diffusiophoresis while differences of temperature between atmosphere and wall of multiple volumes affect thermophoresis.

        Speaker: Mr. Wasin Vechgama (Thailand Institute of Nuclear Technology)
    • 09:00 10:40
      Oral 3: Block IV: Newton Neutron Applications Workshop 1
      • 09:00
        Neutron Scattering for Life Sciences 30m

        Small-angle neutron scattering (SANS) and neutron reflection (NR) have become invaluable tools to life sciences researchers as they allow for determining size, shape and interactions on the nanometer scale in a variety of multi-component systems. Neutrons have specific advantages over X-rays and light. They have a high penetrating power, they are non-destructive, they have a magnetic moment and they scatter from materials by interacting with the nucleus of an atom. The final point is one of the most significant features of neutron scattering when studying multi-component systems. Indeed the neutron scattering power of atoms varies, randomly, from element to element and isotope to isotope. Also, importantly, this dependence allows isotopes of the same element to have substantially different scattering powers and so by altering the isotopic content of a sample (switching the solvent from H$_2$O to D$_2$O) or by using isotopic substitution within a molecule (D for H) specific areas of interest within the system under investigation can have their scattering power enhanced without appreciably changing the chemical properties of the sample. Here, I will present three systems where we used SANS and/or NR: a nanodisc-stabilised membrane-binding protein, a hydrogel for injectable drug delivery and a skin cream formulation.

        Speaker: Dr. Najet Mahmoudi (ISIS Facility, STFC, Rutherford Appleton Laboratory)
      • 09:30
        Neutron Diffraction Techniques and Its Application in Engineering Sciences and Industry 30m

        Research based neutron sources offer a number of opportunities to study problems ranging from fundamental physics to application in the industry and everything in between. In this talk I will be covering the later part of this range focusing on problems of the industrial nature and some examples of materials research. Starting from general introduction of how a neutron source operates, I will introduce the technical and non-technical aspects of specific neutron techniques used for industrial applications. In particular, I will talk about the neutron imaging techniques, neutron based stress measurements and other techniques relevant to engineering sciences (texture, phases, twinning etc.). I will be presenting case studies to highlight how these techniques are being used to solve real world problems. Most of my examples will come from the ISIS neutron source, which is one of the world’s leading neutron sources located in Oxfordshire in the UK. I will end with a general perspective on the future of neutron sources and techniques both in the UK and globally.

        Speaker: Dr. Saurabh Kabra (STFC-UKRI)
      • 10:00
        Utilization of TRIGA PUSPATI Reactor in Various Applications 20m

        Nuclear Malaysia is hosting the only one 1 MW thermal research reactor after being critical in 28 June 1982. Since then, many works have been done in utilizing this reactor for various type of applications. These are including Neutron Activation Analysis (NAA), Small Angle Neutron Scattering (SANS), Neutron radiography and Imaging (NURI), Production of some radio-pharmaceutical and radioisotopes for tracer applications and etc. In order to enhance the utilization neutron beam applications, several new instrument have been developed such as the neutron diffractometer (ND) utilizing bending crystal and prompt gamma neutron activation analysis (PGNAA). These recent development and some results obtained from the instrument will be presented in this article.

        Speaker: Dr. Muhammad Rawi Mohamed Zin (Malaysian Nuclear Agency)
      • 10:20
        The Principle of the Neutron Diffraction Technique for Residual Stress Measurement 20m

        Structural failure is a critical phenomena in construction industry. Failure occur due to the presence of residual stress combined with service stress that over the safety limit. Residual stress is the stress that exists within a material without application of an external load. There are few method for determination of residual stress. In order to study the potential failure consistently, Malaysian Nuclear Agency managed to upgrade the existing facilities, including the development of new facilities as well as human capital. These facilities include Neutron Radiography, SANS, PGNAA, Neutron Diffraction and Reactor simulator. Nuclear Malaysia is committed in developing education and training programs with the fact that nuclear science and engineering are important parts of the knowledge that can provide betterment to the civilization of the people. Neutron diffraction is a non-destructive method of determination of residual stresses in crystalline materials. Neutron diffraction provides the values of elastic strain components parallel to the scattering vector which can be converted to stress. It's measures strain components from changes in crystal lattice spacing. In this paper, the principle of the neutron diffraction technique will be discuss for measuring the residual stress of the crystalline material.

        Speaker: Mr. Zaifol Samsu (Malaysian Nuclear Agency)
    • 10:40 11:00
      Coffee Break 20m
    • 11:00 12:20
      Oral 4: Block V
      • 11:00
        Measurement of Natural ($^{40}$K, $^{226}$Ra and $^{232}$Th) and Anthropogenic ($^{137}$Cs) Gamma Radiation and Radiological Hazard Assessment in Beach Sand Samples Collected from Ao Phrao at Kho Samet in Rayong Province (Thailand) 20m

        In the present research, the main objectives were to measure and analyze the specific activities of natural ($^{40}$K, $^{226}$Ra and $^{232}$Th) radionuclides in 30 beach sand samples collected from Ao Phrao after the Rayong oil spill disaster. This huge Petroleum Authority of Thailand (PTT) oil spill occurred on July 27, 2013, in the Gulf of Thailand nearby Ao Phrao at Koh Samet in Rayong province in eastern region of Thailand. At the same time, anthropogenic ($^{137}$Cs) radionuclides accumulated in the studied area was also studied and presented. High-purity germanium (HPGe) detector with a massive lead shield, some standard reference material sources and gamma spectrometry technique, were used to measure and analyze all of the experimental results. The frequency distribution of specific activities of $^{40}$K, $^{226}$Ra, $^{232}$Th and $^{137}$Cs were also evaluated and found to be the asymmetrical distribution. The median values of $^{40}$K, $^{226}$Ra, $^{232}$Th and $^{137}$Cs were 173.55 ± 67.04, 10.76 ± 1.71, 6.35 ± 0.75 and 0.24 ± 0.10 Bq/kg, respectively. Furthermore, the associated radiological hazard indices for the studied area were calculated and compared to nationally and internationally recommended values. It was found that the beach sand samples from the study area provide no excessive exposures created from the oil spill for inhabitants. Moreover, the radioactive contour maps of the investigated area were also imaged and presented in this study. The data presented in the study are importance since they create the baseline of the radiological hazard data and mapping of the investigated area in the future.

        Keywords: natural and anthropogenic radionuclides, beach sand, Ao Phrao, high-purity germanium (HPGe) detector, radiological hazard index

        Speaker: Dr. Prasong Kessaratikoon (Nuclear and Material Physics Research Unit (NuMPRU), Department of Basic Science and Mathematics, Faculty of Science, Thaksin University, Songkhla Campus)
      • 11:20
        Study of the Factors Influence on Variation of Be-7 Concentration in Surface Air at Osaka, Japan 20m

        Be-7 (T$_{1/2}$ = 53.3 d) is a natural cosmogenic radionuclide and it is widely used as a natural radiotracer in many environment processes, such as atmospheric and local cycling paths of transport. Thus the purpose of this study is to examine and explain the factors that cause variation of Be-7 concentration in the area and during a period of time of the study. Weekly airborne dust samples was continuously collected by using the high volume air sampler (HV - 1000R, SIBATA) with the glass fiber (GB-100R, 203 $\times$ 254 mm$^2$, 0.3 µm pore size) at Daito, Osaka (34.71 N, 135.64 E) during April 18 – December 24, 2016 and January, 8 – May 28, 2018. The filter was measured by HPGe detector (GX2018, CANBERRA). The intensity of 477.6 keV gamma peak was used to obtain the concentration of Be-7 in mBq/m$^3$. The Be-7 concentrations at Daito (2016) was compared with our previous study (Daito 2015) and Sakai (1983 – 1997), we found that a maximum value of Be-7 concentration in spring and autumn and a minimum value and minimum value in summer. In summer, the wind blows from SSW and SW. It is well known that the air mass from low latitudes carries low concentration of Be-7. For the factors causing, we found the negative correlation in rainfall (CC= –0.60±0.12 and sunspot number (CC= –0.41±0.16) and positive correlation in cosmic ray intensity (CC = 0.71±0.16) and PM2.5 (CC=0.32±0.18). Since April 19, 2018, rainwater was collected and we will analyze and report it.

        Speaker: Pannipa Noithong (Graduate School of Human Environment, Osaka Sangyo University)
      • 11:40
        A Car-Borne Radiation Survey and Data Management System for Wide-Area and Quick Survey of Gamma Radiation 20m

        A new car-borne gamma radiation survey and data management system has been developed in order to enable a wide-area and quick survey of gamma radiation level in an environment. The data on gamma radiation level can be used to create an area mapping of baseline gamma exposure which is useful for identifying irregular spots that may appear in the area. These spots may be the consequences of an unintentional radiation accident that happens nearby, someone intentionally leaving a radioactive source to cause harm to passer-by, or a change in commercial activity in the area (e.g. mining). The new system utilizes a large NaI(Tl) detector and is also equipped with gps receiver and camera (optional) that can synchronously record radiation, location, and visual data. The system also has data management software that can store important information in a remote database as well as recall the information for later analysis. The software has been designed to accommodate multiple detectors. Result of the comparisons between the new system and a conventional system will be presented.

        Speaker: Dr. Phongphaeth Pengvanich (Department of Nuclear Engineering, Faculty of Engineering, Chulalongkorn University, Bangkok, Thailand)
      • 12:00
        Determination of Tritium Levels in Tap Waters Collected from Various Regions in Thailand Using Liquid Scintillation Counting 20m

        H-3 (Tritium: Half life = 12.3 a) is a naturally common radioisotope of hydrogen containing 2 neutrons and 1 proton, produced by interaction between fast neutron and nitrogen in atmosphere. Tritium can replace a hydrogen atom in the water molecule since oxygen atom can react with tritium atom to form a water molecule instead of hydrogen atom. This study aims to measure the tritium activity concentration in tap water samples collected from different regions in Thailand, Payao, Srisaket, Chanthaburi, Trang and Bangkok during November 2018. The measurement of tritium activity concentration can be done by using low background liquid scintillation counting (Hitachi-Aloka LB-7) with RO pure water apparatus provide a sensitivity less than 1 Bq/L. The data results of regional distribution of a tendency will be discussed by latitude and longitude. Compare to our previous study at eastern part of China, the results show that the tritium activity concentration depends on localities. Besides, there is no anthropogenic Tritium source in Thailand, the data results can be used for the database of Tritium level in tap water in each region of Thailand before building or operating the facilities such as first nuclear power plant, fuel reprocessing or heavy water production facilities in the future.

        Speaker: Mr. Anawat Rittirong (Osaka Sangyo University)
    • 11:00 12:30
      Oral 4: Block VI: Newton Neutron Applications Workshop 2
      • 11:00
        Present Status and Perspective of Industrial Applications using Neutron Beam Techniques at HANARO 30m

        HANARO (30MW) is a powerful neutron source with a liquid hydrogen cold source. Several neutron beam facilities for industrial applications such as a powder diffractometer, a residual stress instrument, two neutron image facilities, two SANS, and so on, are currently under operation. Recently, two inelastic scattering facilities for use in dynamic material studies are under commissioning. In the future, we plan to develop a thermal neutron guide system with several industrial dedicated neutron beam instruments at HANARO. In this presentation, I would like to present the status and future plan of the neutron scattering facilities at HANARO, and some results of collaborative researches with several industries.

        Speaker: BaekSeok Seong (KAERI)
      • 11:30
        Recent Advances in Research and Application of Neutron Activation Analysis at the Dalat Research Reactor of Vietnam 20m

        Further developments of Neutron Activation Analysis (NAA) have recently been conducted in the Dalat research reactor (DRR) of Vietnam. Besides the single irradiation on the research reactor it is to be the cyclic irradiation mode; Besides the use of total neutron spectrum it is to be the epithermal neutrons; The measurement of prompt gamma-rays (PGNAA) is to be used besides the delay gamma-rays. Moreover, applications of NAA to be not only for environmental, geological and biological specimens but also extended for archaeological and forensics science studies. Particularly, the successful introduction of a modern (so-called k0-standardization method which – combined with a home-made software package namely “k0-DALAT” – made NAA at the DRR as a regionally appreciated laboratory. Brief of recent advances of NAA in DRR: (a) Development of the cyclic and pseudo-cyclic NAA; (b) Development of the epithermal NAA; (c) Application of the k0-standardized method for PGNAA; (d) Extension of NAA applications to archaeology and forensics science, will be talked in the presentation.

        Keywords: Neutron Activation Analysis, k0-standardization method, Cyclic activation, Epithermal neutron NAA

        Speaker: Dr. Manh Dung Ho (Center for Nuclear Techniques, Vietnam Atomic Energy Institute)
      • 11:50
        Defect-induced Room-temperature Magnetism in Superconducting Ln$_{2-x}$Ce$_x$CuO$_{4+d}$ (Ln = Pr, La) Nanocrystals 20m

        In the past few years, magnetic spins in the non-magnetic compounds have been studied intensively to reveal the origin of so-called room-temperature ferromagnetism in any nanoparticles. The materials having partially filled d or f shells exhibit various kinds of magnetic properties, especially ferromagnetic properties. It is known that the properties of ferromagnetism and its superconductivity are contradictory in the superconducting high-Tc cuprates. However, it has been observed that there is coexistence of ferromagnetism and superconductivity in nano-sized powders, such as YBa$_2$Cu$_3$O$_7$ (YBCO), Bi$_2$Sr$_2$CaCu$_2$O$_8$ (Bi-2212), and Pr$_{2-x}$Ce$_x$CuO$_4$ (PCCO) nanoparticles. The ferromagnetism in the nanoparticles has been suggested to be occurred on the surface. This magnetism has been expected coming from defects inducing magnetic moments on oxygen vacancies (crystalline point defects) at the surface of the nanoparticles. However, this should be clarified in much more detail. This work is to elucidate the origin of magnetism due to defects in non-magnetic nanosized superconductors for n-type cuprates, Ln2-xCexCuO4 (Ln=Pr,La), by means of neutron diffraction and scattering instruments for determination of oxygen occupancies corresponding to the magnetic structure of the T’-cuprates. Magnetization curves from SQUID measurements for Ln$_{2-x}$Ce$_x$CuO$_4$ (LnCCO) have revealed that there is weak ferromagnetism observed at room temperature. Moreover, EXAFS analysis of the LnCCO nanocrystals have indicated the change of oxygen content through reduction annealing.

        Keywords: Defect. Ferromagnetism, Ln$_{2-x}$Ce$_x$CuO$_4$, Nanocrystals, Oxygen vacancy

        Speaker: Malik Anjelh Baqiya (Department of Physics, Institut Teknologi Sepuluh Nopember (ITS) Surabaya)
      • 12:10
        Unravelling Specific LPS Binding Sites on Gram-Negative Trimeric Porins by Neutron Scattering 20m

        Escherichia coli (E. coli) are gram-negative bacteria commonly found in human guts but which can cause food poisoning or severe systemic infections such as meningitis. Unlike other bacteria, gram negative cells have an additional asymmetric outer membrane (OM) which consists of outer membraneproteins and tightly-packed lipopolysaccharides (LPS) in the outer leaflet of membrane and phospholipids on the inside. The OM is a highly impermeable barrier and protects E. coli from toxin, antibiotics and bile acids. However, little is known about how OM organizes especially the interaction between outer membrane proteins and LPS. This interaction could play a vital role in the OM integrity and impermeability. Here we reveal the specific interactions between the trimeric porins of E. coli and LPS. The structure of complexes was determined by small angle neutron scattering (SANS) and utilizing a contrast variation strategy with selective deuteration of proteins, LPS and sodium dodecyl sulfate (SDS). Mixing of two SDS forms achieved exact contrast matches with the solvent. This enabled us to observe the specific interaction of LPS and porins which also confirmed by mutagenesis results and high-resolution X-ray crystal structure.

        Speaker: Dr. Wanatchaporn Arunmanee (Department of Biochemistry and Microbiology, Faculty of Pharmaceutical Sciences, Chulalongkorn University )
    • 12:30 13:30
      Lunch 1h
    • 13:30 14:40
      Oral 5: Block VII
      • 13:30
        Novel Applications Using Beam’s Eye View (BEV) Imaging in Radiation Therapy 30m

        External beam radiation therapy (known as radiation therapy) is a local cancer treatment that uses high radiation dose to damage the deoxyribonucleic acid (DNA) of cancer cells with specific part of patient body. A linear accelerator (linac) customizes high energy x-rays or electrons to conform to a tumor’s shape and destroy cancer cells while sparing surrounding normal tissue. Beam’s eye view (BEV) imaging technique is used for quality assurance (QA) and treatment planning of radiation therapy to ensure the relative orientation of patient and beam delivery of linear accelerator (linac) machine. The common x-ray image device for linac includes Megavoltage (MV) electronic portal imaging device (EPID) and Kilovoltage (kV) cone-beam CT (CBCT) imaging devices. These devices were initially designed for patient localization purpose. However, the use of EPID and CBCT has been applied for other clinical aspects; such as linac QA, pre-treatment patient-specific QA, motion tracking, and real-time patient verification. In this talk, an introduction of BEV technique as well as the advantage and disadvantage between EPID and CBCT devices will be summarized. Overview of the novel applications that use the BEV imaging technique for clinical use will be presented. It also covers from a real-time data collection using frame grabber card and external workstation connected to linac machine, real-time marker and markerless tumour tracking, patient-specific EPID-based QA, comprehensive VMAT QA, remote auditing, intra and inter-fraction patient treatment verification, and clinically significant anatomical change in cancer patient during treatment course.

        Speaker: Dr. Todsaporn Fuangrod (Chulabhorn Royal Acadamy)
      • 14:00
        CTScanTool, a Semi-automated Organ Segmentation Tool for Radiotherapy Treatment Planning 20m

        The goal of radiotherapy is to eradicate tumors while sparing healthy tissues from radiation damage. Therefore, accurate definition of tumor and organ boundaries is important for achieving good treatment outcome. Organ segmentation is a standard procedure done in radiation therapy treatment planning. Computed tomography (CT) images are commonly used for this purpose. In this paper, we present the development of CTScanTool, the semi-automated organ segmentation tool developed in MATLAB with the graphical user interface. The segmentation method is combined between region growing, morphological reconstruction and watershed transform algorithms. The semi-automated segmentation results of CT images were compared with those contoured by an experienced radiation oncologist. In the experiment, we investigated the combined segmentation method on brain, lung and kidney tissues. In all cases, the agreement was better than 90% for the dice coefficient and the true positive rate-based evaluation. In the near future, CTScanTool will be incorporated in the Proton pencil beam Scanning treatment PLANning system (PSPLAN), which can be used for research and education in proton therapy.

        Speaker: Thiansin Liamsuwan (Thailand Institute of Nuclear Technology)
      • 14:20
        Role of Gap Junction Communication between Carbon-Irradiated Glioblastoma and Bystander Normal Cells Through Activation of NRF-2 Antioxidant System 20m

        Glioblastoma (GBM) is the most aggressive and common primary brain tumors.This results in resistance to current treatment by low linear energy transfer (LET radiation such as X ray. In addition, many side effect of cisplatin are major drawbacks in radiation therapy of GBM patients. Hence, the aim of the study was to investigate the toxicity of combined high linear energy transfer (LET) carbon ions with cisplatin in bystander normal cells. Briefly, confluent GBM (T98G) cells were treated with cisplatin, followed by carbon ions. Within 20 min following exposure, carbon-irradiated T98G cells were trypsinzied and seeded on the top of insert with bystander normal NB1RGB cells in the presence and absence of gap-junction inhibitor (AGA) at the bottom of it and assayed for further analysis. Our results show that gap junction intercellular communication (GJIC) enhances cisplatin toxicity from carbon-irradiated T98G cells to bystander normal NB1RGB cells. However, the cytotoxicity in the bystander normal cells can be partially suppressed by inhibiting of GJIC. Consequently, the protective mechanism of AGA against the toxic effect of radiochemotherapy was assessed based on the restoration of the antioxidant defenses via activation of Nrf2. This study demonstrates that GJIC inhibitor is a new candidate that the radioprotective effect in bystander normal cells and its combination with high LET carbon ions, is promising method in GBM patients.

        Speaker: Dr. Narongchai Autsavapromporn (Chiang Mai University)
    • 13:30 14:40
      Oral 5: Block VIII
      • 13:30
        Micelle-Mediated Extraction followed by Neutron Activation for Simultaneous Determination of Trace Elements and their Species in Water 30m

        Concentrations of many elements in natural waters are generally below the detection limits of most instrumental analytical techniques thereby necessitating their preconcentration. Liquid-liquid extraction has been widely used for this purpose. Nonionic type surfactants offer the best alternative to conventional extraction methods. These surfactants have a critical point (a.k.a. cloud point) above which two isotropic phases are well defined: a dilute aqueous phase containing low concentrations of surfactant and a surfactant-rich phase. Any species that binds to the micellar entity in solution can be subsequently extracted into the surfactant-rich phase. We have been developing micelle-mediated extraction, commonly called cloud point extraction (CPE), procedures in conjunction with neutron activation analysis for the simultaneous determination of a number of elements and their species since 1995. We have studied phase diagrams of PONPE-7.5 and -20, and partition coefficients of PAN and TAN. We have developed CPE methods for: (i) Cd, Co, Cu, Mn, Ni and Zn, (ii) Dy, Er, Eu, Gd, Ho, La, Lu, Pr, Sm, Tb, Tm, and Yb; (iii) Cd, Cr, Hg and Zn; (iv) V; (v) Sb; and (vi) As(III) and As(V) species. A preconcentration factor of 60 and detection limits of 0.03-25 µg kg-1 have been achieved.

        Speaker: Prof. Amares Chatt (Dalhousie University)
      • 14:00
        Assessment of Colorimetric Reading out Methods for Radiochromic Film and Red Radiation-Sensitive Poly-Methylmethacrylate. 20m

        This research is aimed to introduce and to compare 3 methods of reading out and analysing light blue radiochromic film (BLF) dosimeter and red radiation-sensitive poly-methylmethacrylate (PMMA). BLF and red radiation-sensitive PMMA act as a colour detector which its colour changes after being irradiated. These dosimeters are usually used in food irradiation for process control during irradiation process. We used camera-based measurement in a constraint condition, scanner-based measurement with our own software (Trichromatic Colour Analyser, TCA) and spectrophotometer for obtaining colorimetric data of both dosimeters which were non-irradiated and irradiated in 5 different doses: 5, 10, 15, 20 and 25 kGy, ranged for food application. There were strong linear relationships, for all 3 methods, between doses, given to BLF, and lightness (CIE L$^*$), chroma (CIE C$^*$) and yellowness-blueness (CIE b$^*$). For red radiation-sensitive PMMA, strong linear relationships were found between doses and redness-greenness (CIE a$^*$) as well as CIE C$^*$ in both TCA and spectrophotometer methods. The doses and CIE L$^*$ gave strong relationship only in the spectrophotometric method.

        Speaker: Mr. Teesit Varapaskul (Dept. Imaging and Printing Technology, Faculty of Science, Chulalongkorn University)
      • 14:20
        Evaluation of Geometry Correction Factors for a Cylindrical Nested Neutron Spectrometer System 20m

        This work presents the evaluation of geometry correction factors as functions of distances from the source and the dimensions of different moderators for a cylindrical nested neutron spectrometer (CNNS) system with a $^6$LiI(Eu) thermal neutron detector located at the moderator centers. The ISO 8529-2 only mentions these correction factors for a spherical neutron spectrometer (i.e., Bonner sphere spectrometer) but not for other shape ones as well as for a CNNS. In this work, MCNP6 simulations have been conducted for evaluating these correction factors in the case of the CNNS is irradiated from the side to an X14 encapsulation type $^{241}$Am − Be neutron standard source. The relationship of the correction factors as functions of distances from the source and the dimensions of different cylindrical moderators was also proposed and presented for the convenient uses of routine calibrations.

        Speaker: Mr. Ngoc Quynh Nguyen (Institute for Nuclear Science and Technology)
    • 14:40 15:50
      Poster 2: Poster Session II
      • 14:40
        68Ga-Labelled Ubiquicidin for Monitoring of Mouse Infected with $\textit{Staphylococcus aureus}$ 1h

        Ubiquicidin is a cationic, antimicrobial peptide found in the innate host defense against pathogens. The peptide is selectively interacted with the surface of microorganism. This work aimed to develop the radiopharmaceutical for infection imaging using antimicrobial peptide. Optimum labeling condition to obtain $^{68}$Ga-DOTA-ubiquicidin (29-41) with radiochemical purity (RCP) more than 90% was evaluated. The RCP was more than 95% with 30 micrograms peptide at solution reaction pH 4. Stability testing of the labeled peptide resembling to in vitro condition using fresh frozen human plasma was studied. The radiolabeled peptide retained its RCP >90% after 4 hours of incubation. Accumulation of $^{68}$Ga-DOTA-UBI at left thigh of mice infected with $\textit{Staphylococcus aureus}$ was greater than that mice inoculated with sterilized S. aureus (inflamed mice) with %ID/g of muscle at 120 minutes were 4.62 ± 3.44 and 1.53 ± 1.73, respectively. These results showed the efficacy of $^{68}$Ga-DOTA-UBI as a radiopharmaceutical for monitoring of bacterial infection.
        Keywords: antimicrobial peptide, ubiquicidin, Ga-68

        Speaker: Ms. Wiranee Sriwiang (Thailand Institute of Nuclear Technology (Public Organisation))
      • 14:40
        Analysis of Radiological Hazards from Surface Soils in Khong Chiam and Sirinthon District Ubon Ratchathani Province 1h

        The radiological hazards from natural radionuclides in soil at the border area between the southeast of Thailand and Laos were studied and evaluated. The 33 surface soil samples from Khong Chiam and Sirinthon districts in Ubon Ratchathani province were collected and measured the specific radioactivity of $^{226}$Ra, $^{232}$Th and $^{40}$K. The radioactivity of all soil samples was analyzed from gamma ray spectrums using Hyper-Pure Germanium (HPGe) detector. The results applied for calculating the radiological hazards which were radium equivalent activity (Raeq), absorbed dose rate (D), annual effective dose equivalent (AEDEout) and external hazard index (Hex). The experimental results obtained the radioactivity concentrations in a range of 10.64 to 46.67$^{-1}$ with average value of 22.82 3.59$^{-1}$, 6.35 to 44.72$^{-1}$ with average value of 15.49 $\pm$ 3.57 and 31.22 to 521.57$^{-1}$ with average value of 130.44 $\pm$ 28.46$^{-1}$ for $^{226}$Ra, $^{232}$Th and $^{40}$K, respectively. The calculation results of Raeq, D, AEDEout and Hex showed significantly lower than the radiological hazard levels which are recommended by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). The results of this study reveal that people can live and travel along the border area in the southeast of Thailand.

        Speaker: Mr. Manit Jitpukdee (Department of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University)
      • 14:40
        Application of Compact Disc for Photo-Neutron Measurement Generated from High Energy Photon Irradiated by 10 MV Medical Linear Accelerator 1h

        The high energy photon from medical linear accelerator (Linac) have been widely used for cancer treatment with radiotherapy. However, when high energy photon interact with Linac head components the undesirable neutrons contamination can be produced by photo-nuclear reaction. This work aims to evaluate photo-neutron dose generated from Linac 10 MV. The polycarbonate base layer of compact disc (CD) has been applied to neutron dosimetry by combining with polyethylene converter and boron converter for the fast neutrons and the thermal neutrons measurement, respectively. The pieces of CD track detector were irradiated with high energy photon from 10 MV Elekta Precise Linacs in the solid water phantom at depth of 0, 2.5, 5, 10, 15 and 20 cm, then etched with PEW solution (potassium hydroxide, ethanol and water) with ratio of 15: 45: 40 at various solution’s temperature and etching times. The neutron response of CD track detector, CR-39 track detector and MCNP simulation have been compared. The results showed that the shape of the fluence responses of neutron and the neutron dose equivalent of them were agreed. This CD track detector for neutron measurement system allows users to measure all energy ranges of neutrons produced in the radiotherapy room more easily.

        Keywords: LINAC, Photo-Neutron, Neutron measurement, Compact disc, CR-39, MCNP

        Speaker: Mr. Porama Thepsiri (Faculty of Associated Medical Sciences Chiang Mai University, Chiang Mai, Thailand )
      • 14:40
        Comparison of the FRACAS and FEA Mechanical Models Impact on the Fuel Rod Performance and Failure Simulation 1h

        Fuel rod performance is an important part of the modern reactor core analysis codes. In order to test and confirm the reactor core safety, one who performs the core design needs of some hypothetical scenarios calculation conducted with the fuel rod failure accidents. Two types of failure accidents are commonly considered: extra reactivity insertion accident (RIA) and loss of coolant accident (LOCA). The accidents could lead to the pellet-cladding mechanical interaction with a large cladding deformation and burst on the last simulation stage. Accurate simulation of the large cladding deformations requires the two- or three- dimensional modeling that is able to catch the real cladding reshaping and properly predict its critical stress and strain points. In our research, we compare the one-dimensional model FRACAS-I and finite element model FEA provided by the fuel performance analysis code FRAPTRAN. We calculate the accident benchmark using the REP-Na8 and compare the thermal-mechanical response between both models. The calculation shows a significant difference between the results of thermal radial gap, cladding hoop stress and cladding hoop strain. The FEA's results show similar response to the physical experiment data. We recommend that FEA mechanical model is suitable for further entire core simulation analysis.

        Speaker: Mr. Korawit Saeju
      • 14:40
        Consideration of Scope of Probabilistic Safety Assessment of Thai Research Reactor1/Modification1 (TRR-1/M1) 1h

        To systematically confirm safe operation of the Thai Research Reactor-1/Modification 1 (TRR-1/M1), Probabilistic Safety Assessment (PSA) can be used to quantify risks of the reactor, design protective and mitigative strategies. In the 2015 Annual Meeting of Regional Advisory Safety Committee for Research Reactors in Asia and the Pacific (RASCAP), the IAEA recommended the Member States to start performing a Periodic Safety Review (PSR). PSA can be included as a part of the PSR. Reactor Safety Advisory Group (RSAG) of the TRR-1/M1 agreed with the IAEA’s recommendation, which is in line with the requirement by Ministerial Regulation on Schedule of Review and Update of Safety Analysis Report of Nuclear Facilities to perform a PSR once every ten year. There was an attempt to perform a PSA for the TRR-1/M1, though the scope was insufficient and the input data was not specific to the TRR-1/M1. Therefore, this paper aim is to reconsider the scope of the PSA for the TRR-1/M1 based on practice of nuclear power plants and apply graded approach recommended by the IAEA. Appropriate scope will help systemize the implementation of PSA, which will clarify responsibilities of each sector to contribute prevention and mitigation of accident.

        Speaker: Wasin Vechgama (Thailand Institute of Nuclear Technology)
      • 14:40
        Creating the Networks of Monitoring and Internal Dose Assessment due to Intake of Iodine-131 by Using Thyroid Uptake Counters and Gamma Camera 1h

        The objective of this paper is to create networks of measuring and assessing internal dose due to intake iodine-131 using either thyroid uptake counter or gamma camera, which is currently mostly used in nuclear medicine facilities. There are thirteen nuclear medicine volunteers participated in the activity. Among the network, thyroid uptake counter technique was used by twelve representatives and gamma camera was used by one. All participants were trained to measure iodine-131 and assess internal dose base on IAEA safety series no.114 and ICRP 78. The efficiency calibrations with iodine-131 standard were performed for all participated instruments, in order to ensure that those systems are suitable for iodine-131 measurement of the interested samples, including thyroid, charcoal filter paper, contamination filter paper and a bottle of 5 ml urine. Then, internal doses were assessed. The efficiency of those iodine measurements were reported in the paper. After the evaluation, it is found that MDA values from all participants were lower than derived recording level (DRL), implying that their environments are suitable for measuring iodine-131. In some networks, however, MDA values were slightly higher than DRL. Therefore, decreasing background level to improve MDA to be lower than DRL is recommended to improve the efficiency of the measurement.

        Keywords: internal dose, thyroid uptake, gamma camera, iodine-131, thyroid counting

        Speaker: Mrs. Darunee Peekhunthod (Office of Atoms for Peace)
      • 14:40
        Determination of Neutron Generated in Self-Shielded Medical Cyclotron Facility 1h

        HM-20S self-shielded medical cyclotron is used in PET radiopharmaceutical production. During operation, neutrons were generated by (p,n) reaction between primary beam and target or cyclotron’s part. High energy neutrons can penetrate or slow down and activate cyclotron’s component to be radionuclide. The dose from activated radionuclide will cause radiation exposure to cyclotron operators, radiopharmacists, maintenance workers and public. The purpose of this study is to measure generated neutrons in cyclotron facility at the Siriraj Cyclotron Center, for consideration of the radiation safety in routine operation and to predict radiation dose from activated components. Determination of neutron inside shielded area using neutron capture gamma ray of aluminum plates placed on positions, and HPGe spectrometer for counting gamma radiation. Inside and outside the cyclotron vault area neutrons were measured by using CR-39 track detector. The measured neutron fluxes inside cyclotron vault were 227, 160, 6.19, and 120 cm$^{-2}$s$^{-1}$/µAh on shielding wall and 338, 94.1, 35.9, and 65 cm$^{-2}$s$^{-1}$/µAh on vault’s wall. For outside cyclotron vault, the neutron fluxes were not more than background level. The predicted dose rate by measured neutron flux and activation calculation formula were less than 1 µSv/h after routine operation.

        Speakers: Mr. Tanapol Dachviriyakij (Office of Atoms for Peace , Ministry of Science and Technology ), Ms. Apisara Charoensri (Office of Atoms for Peace , Ministry of Science and Technology )
      • 14:40
        Development of Absorbed Dose for Radiotherapy Level Using EPR Dosimeter 1h

        The aim of this research is to develop the method to measure the absorbed dose for radiotherapy level in the range of 1-10 Gy using EPR dosimeter. The parameters for measuring the absorbed dose using EPR dosimeter consist of microwave power, modulation amplitude, ratio of time constant: conversion time and number of scans have been used in this study. The results showed that the optimal parameters for measuring the absorbed dose in the range of 1-10 Gy were in the following; microwave power was 3.15 MW, the modulation amplitude was 17 G, the time constant: conversion time ratio was 4:1 and the number of scans was 10. The coefficients of determination between the dose from 1 to 10 Gy and the EPR signal generated from the optimal parameters was 0.9995. The accuracy of the developed method was more than 99% when compare with the ASTM E1026 standard method. It can be concluded that the optimal parameters used in the developed method can be used to determine the absorbed dose for radiotherapy level.

        Keywords: absorbed dose, radiotherapy level, EPR dosimeter

        Speaker: Mrs. Sumalee Ninlaphruk (Office of Atoms for Peace)
      • 14:40
        Elemental Composition Analysis in Sangyod Muang Phatthalung Rice by Instrumental Neutron Activation Analysis 1h

        Sangyod Muang Phatthalung Rice is a traditional rice variety grown in the area of Phatthalung province for more than a hundred years. Sangyod rice is the first rice variety of Thailand that has been registered as Geographical Indication (GI). It is also good rice for anyone who is searching for good health. The concentrations of elements (Mg, Al, Cl, As, Br, K, Mn, Rb and Zn) in Sangyod rice, locally cultivated in four districts (Pak Phayun, Tamot, Pa Phayom and Muang) in Phatthalung province, were determined using instrumental neutron activation analysis (INAA). The method validation of INAA was verified by SRM 1568a Rice Flour. All elements were found to be in a good agreement with the certified values. The results were analyzed using analysis of variance and Tukey’s HSD test. There were no statistical differences in concentrations of Mg, Al, As, Br, K and Mn in rice from four districts. The concentrations of Cl, Rb and Zn found in rice were significantly different according to the cultivation region. Therefore, Cl, Rb and Zn were good characteristic indicators for Sangyod rice that could be applied to identify the geographical origins of rice.

        Speaker: Dr. Supalak Kongsri (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:40
        Environmental Radiation Monitoring Management Plan for Atmospheric Pathway 1h

        Radionuclides in the environment are from natural occurrence and man-made activities. For the later source, it can be from nuclear weapon testing, nuclear accidents and nuclear applications using as in medical, industrial sectors and research that are able to increase some artificial radionuclides to the terrestrial ecosystem. These radionuclides can enter to human by inhalation, ingestion and skin absorption. The significant amounts of radionuclides entered to human body would have some biological effects. According to the various laws and guidelines, the radiation control is strictly managed in facilities using nuclear and radioactive materials. Therefore, the efficient radiation monitoring system for terrestrial ecosystem is very important for determining environmental status in normal situation and nuclear emergency situation. The appropriated factors and parameters management in properly selected pathway can be used for dose assessment. This research is to present the environmental radiation monitoring management plan for pathway from atmosphere to human by uptake. This designed management plan would be used for a guidance of radiation monitoring system which is corresponding to international standards.
        Keywords: environmental radiation monitoring, radionuclides, atmospheric pathway

        Speaker: Ms. Suprawee Siriboonprapob (Office of Atoms for Peace, Regulatory Technical Support Division)
      • 14:40
        Estimation of External Gamma Radiation Dose Rate for Personnel and Students in the Area of Kasetsart University, Thailand 1h

        Kasetsart University, Bang khen is surrounded by several radiation agencies. In order to reduce concerns and confirm on radiation safety for university personnel and students, 130 points of the ambient gamma dose equivalent rate (H*(10)) were measured above the ground at 1 m and mapping around this area using a NaI(Tl) scintillator, 63×63 mm, including natural radioactive elements (K-40, Th-232, and U-238) from soil were collected in the 10 cm soil layer for 13 samples for investigating the natural background radiation. The gamma dose rates in air obtained were found between 0.09 µSv/h – 0.26 µSv/h with the average value was about 0.16 µSv/h. The location of minimum value was found at Kasetsart University Main Auditorium ($13^{\circ}$ 50$’$ 28.3$''$N, $100^{\circ}$ 34$’$ 31.1$''$E), and the maximum value was found at Museum and Insect Park of 60 Years Kasetsart University ($13^\circ$ 51$’$ 12.6$''$N, $100^\circ$ 34$'$ 01.9$''$E). The activity concentration of U-238, Th -232 and K-40 from soil samples were determined using a gamma spectrometry analysis system with HPGe detector, which the average specific activity was also used to evaluate the absorbed dose rates (D) and the annual effective dose (E) for general population in the area.

        Keywords: Radiation, Background radiation, Soil sample, Gamma dose rate

        Speaker: Chanis Pornnumpa (Department of Applied Radiation and Isotopes, Faculty of Sciences, Kasetsart University)
      • 14:40
        Evaluation of Radiation Safety for Ionizing Chamber Smoke Detectors Containing Am-241 1h

        The safety assessment was carried out for ionization chamber smoke detectors (ICSDs) containing 241Am under normal use and accident scenarios. The internal and external dose were estimated using dose coefficients and associated calculation. In normal use of the ICSDs with the activity in a range of 0.002–1 MBq per ICSD, the external dose was evaluated by to an individual for installation, use and maintenance were found to lie in the range of (0.01-4.17)x10$^{-3}$ (0.017-6.76)x10$^{-1}$ and (0.006-2.5)x10$^{-2}$ µSv/y respectively. The activity of 241Am for domestic smoke detectors contain approximately 40 kBq per ICSD. The corresponding committed effective doses to a firefighter during a fire and for cleanup operation after a fire via inhalation were found to be 6.1x10$^{-5}$ and 0.024 µSv/y respectively. The committed effective dose equivalent to an infant due to dismantling of the ICSDs via ingestion would be 148 µSv/y. The possible dose arising from normal use, incidents and misuse of ICSDs are less than 10 µSv/y and 1 mSv/y respectively which do not exceed the dose criteria for exemption from regulatory control. It could be concluded that the individual radiological risk resulting from the normal use, incidents and misuse of the ICSDs are estimated to be very low and lower than 1 mSv which is the annual dose limit to a member of the public for the safe use. However, the design, construction and performance for the ICSDs should comply with the relevant requirements of ISO standard.

        Speaker: Ms. Doendara Malain (Office of Atoms for Peace)
      • 14:40
        Evaluation of Radiation-treated Turmeric Dressing for the Wound Healing Potential in Rat Model 1h

        Curcumin, a naturally derived substance from turmeric, is a well-known topical wound healing agent, which exhibits various properties such as anti-inflammatory, anti-oxidant, and antimicrobial. In this work, we tested the efficacy of crude curcumin prepared from turmeric powder for its wound healing effect in rats. The as-received, commercial Thai turmeric powder was first dissolved in glycerol to make an ointment before sterilization by gamma rays at 25 kGy. HPLC data showed that the curcumin content in irradiated turmeric ointment decreased by about 2.5 folds compared to non-irradiated sample. Full-thickness wounds of size 6 mm in diameter were made surgically on the dorsal side of Sprague Dawley rats, and irradiated turmeric ointment was administered topically. In terms of epithelial healing, wound closure in turmeric-treated rats was observed to be similar to the non-treated group on days 14 and 21 post-wounding. However, histological examination revealed that turmeric better promoted dermal healing as characterized by increasing collagen formation, decreasing granulation tissue, and modulating inflammatory responses especially macrophage and giant cell depositions. Based on these initial results, the use of crude curcumin in irradiated turmeric solution has demonstrated its potential to promote wound healing at the cellular level in animal model.

        Speaker: Dr. Pimpon Uttayarat (Research and Development Unit, Thailand Institute of Nuclear Technology (Public Organization))
      • 14:40
        Fuel Burnup Analysis and Fuel Management for TRIGA Mark III Research Reactor 1h

        The fundamental advantage in using Monte Carlo methods for burnup calculations is to formulate an effective optimal fuel management strategy for the TRR-1/M1 research reactor. The core management study has been performed by utilizing the essentially parameters including multiplication factor, power peaking, neutron flux and burnup calculation based on the Monte Carlo calculation. The fuel element burnup was calculated after reshuffling the reactor core. The fuel cycle length and core parameters such as core excess reactivity, neutron flux, axial and radial power factors and other parameters are determined. The core excess reactivity was calculated as a function of burnup. The maximum excess reactivity shall not exceed 6.3%Δk/k. The maximum fuel temperature shall not exceed 930ºC during steady-state operation. Typically, a core loading operated with the maximum burnup between 100 to 200 MWD depending on the utilization requirements. The thermal neutron flux in the irradiation positions is within the order of 10$^{11}$ - 10$^{13}$ n/cm$^2$-sec. The study gives valuable results into the behavior of the TRR-1/M1 research reactor and will ensure optimized utilization and operation of the reactor during its life time. It will establish the strategic planning for fuel management in the reshuffling and reloading schemes patterns and its safe implementation in the future.

        Speaker: Dr. Kanokrat Tiyapun (Thailand Institute of Nuclear Technology)
      • 14:40
        Improvement of Regulatory Process for Import and Export of Radioactive Sources through Digital Transformation 1h

        Radioactive sources have various utilization in many fields in Thailand including medical, industrial, research and education. Thailand regulatory body, Office of Atoms for Peace (OAP) has been regulating the imports and exports of radioactive sources under the Atomic Energy for Peace Act, B.E. 2504 (1961) and Nuclear Energy for Peace Act, B.E. 2559 (2016) through the licensing process and customs declaration process. Under these processes, licensees must report their imports and exports by submitting confirmation documents to the OAP with in 15 days. To improve these processes, the OAP and Thai Customs have collaborated through a government and government partnership (G2G), in July 2016, to initiate electronic data sharing in a digital format called License Per Invoice (LPI), which includes all the necessary information for verification of import and export, such as radioactivity, port number, and Harmonized System Code (HS Code). The new process enhances information accuracy, integrity, and security, as well as increasing regulation efficiency, reducing the amount of paper work, and better facilitate all stakeholders for import and export of radioactive sources in Thailand.
        Keywords: Import, Export, Radioactive Source, Regulation

        Speaker: Ms. Piyawan Srikongpan (Office of Atoms for Peace)
      • 14:40
        Indoor Radon Gas Level in Ban Pang Faen, Doi Saket Chiang Mai Province 1h

        The purpose of this research was to measure indoor radon concentration in the area of Ban Pang Faen, Pa-Miang subdistrict, Doi-Saket district, Chiang Mai Province. Radon measurements were performed in 59 sites from February 27 to June 24, 2017 for 115 days by using plastic alpha track detectors or CR-39. The results of indoor radon gas concentrations in bedroom and living room were 28±14 to 143±47 Bq/m$^{3}$ and 26±19 to 322±109 Bq/m$^{3}$, respectively. Radon levels in 4 sites were higher than 148 Bq/m$^{3}$ which is taken as the action level by the United States Environmental Protection Agency (U.S.EPA). Then, the average annual effective dose of residents were calculated from radon concentration, using equation, which is introduced by UNCLEAR and were found to between 0.21 to 1.71 mSv/year. The average annual effective dose of 31 residents are above the dose limit of 1 mSv/year recommended by the International Commission on Radiological Protection (ICRP).

        Speaker: Dr. Sompong Sriburee (Department of Radiologic Technology, Faculty of Associated Medical Sciences, Chiang Mai University, Chiang Mai, Thailand)
      • 14:40
        Influence of the High Burnup Structure Modelling on the Fuel Rod Failure Simulation 1h

        The fuel burnup is a key factor influencing the energy production of a nuclear power plant. In order to improve the economic efficiency of a power plant, increase of fuel burnup is needed. The change of oxide fuel thermo-mechanical properties during irradiation is well known and could be accurately simulated if a fuel burnup does not exceed the value 65 GWd/MTU. Otherwise, high burnup structure (HBS) phenomenon appears, which must be taken into account in a simulation. In order to check the effect of HBS on a fuel rod behaviour and failure simulation, the IFA-432 benchmark has been calculated by the FRAPCON fuel performance code. There are two built-in gas release models in the code: the Massih model and FRAPFGR model, that includes the influence of HBS effects. The calculations are conducted for each model. The calculation results show a large difference of the total fission gas release between two models. Also, it was confirmed that the presence of HBS has an impact on a fuel rod damage due to a failure accident.

        Speaker: Mr. Narakhan Khunsrimek (chulalongkorn university)
      • 14:40
        Investigation of the Properties of Aluminum Tube used in Thailand Research Reactor TRR-1/M1 1h

        Thailand research reactor, TRR-1/M1, is a TRIGA Mark-III nuclear research reactor using UZrH fuels with 20% U-235 enrichment. The reactor operated approximately at 1,200 kWth, which produced neutrons maximum flux of 8x10$^{13}$ neutrons-cm$^{2}$ per second and maximum temperature of 600$^{\circ}$C at the hottest spot in the core. Exposure to such high neutron flux and temperature can cause property degradation to the core structural materials. In addition, corrosion is one of major degradation mechanisms for the pooled-type reactor. This paper presents the material degradation analyses of an aluminum (Al6061) tube for neutron irradiation that was detached from the TRR-1/M1 reactor core. The analyses consisted of oxide characterization and radiation hardening measurement. The oxide characterization was done using XRD grazing angle technique for phase identification, and SEM for surface morphology and cross-section investigation. The radiation hardening was evaluated through Vicker-hardness measurement. Preliminary results showed that oxide on the aluminum tube consisted of two layers. Oxide thicknesses on outer side were larger than those of inner side of the tube. Major oxides are Bayerite (Al(OH)$_3$), Gibbsite (Al$_2$O$_3$.3H$_2$0) and Quartz (SiO$_2$). The results revealed that the neutron-captured reaction of Al produced Si. The formation of Si can cause changes in material properties from loss of Al content in bulk material, and by Si precipitation. Therefore the material would degrade after service in the reactor core. Results from the hardness test will be compared with the pre-limitary assessment of the radiation effects by Kinchen-Pease Model. Overall outcome of the study will explain the major degradation mechanisms of the structural materials in the TRR-1/M1, which will lead to suggestions on operation and maintenance for safe operation of the reactor.

        Speaker: Pantip Ampornrat (Office of Atoms for Peace)
      • 14:40
        Long-Term Cyling of Radiocaesium in Pine Forest at Wat Chan Thailand 1h

        This study focused on the long-term cycling of radiocaesium in pine forests at Wat Chan in northern Thailand. Systematic studies were made of stable and radiocaesium, potassium and rubidium in soil horizons, tree stems and needles. Measurements of total concentrations were complemented with determinations of exchangeable fractions as well as the isotopic exchangeability of radio- and stable caesium. Wat Chan in Thailand is a native tropical forest of Pinus kesiya (or Three-needled pine) which received chronic distribution of atmospheric fallout from nuclear weapons tests in the 1960s. Samples were taken from this site in late February 2016 at six randomly located co-ordinates. The forest soil is typical of similar forest soils in the tropical zone. The organic matter, even at the surface, is much less abundant than in temperate forest soils while the mineral soil is composed almost entirely of quartz with no identifiable clay minerals. About 84% of nuclear weapons fallout $^{137}$Cs is distributed within the upper 3 cm and the maximal distribution is 37.6% at 2 cm depth. These inventories were decay corrected to 1963 and summed to provide a total soil profile inventory of 643 Bq m$^{-2}$. Even though the organic matter content in the upper 2 – 3 cm of the soil profile is low it probably still plays an important role in the vertical distribution of $^{137}$Cs. The variation of soil pH throughout the upper 13 cm of the soil profile is less than 1 pH unit and thus is unlikely to influence the vertical distributions of $^{137}$Cs and $^{133}$Cs in the soil. K and Rb are strong competitors of Cs during cycling within the forest ecosystems at Wat Chan. K is present in the exchangeable fraction in soil at much higher concentration than Rb and especially Cs. The overall degree of translocation from soil to pine needles is in the order of $^{39}$K > $^{85}$Rb > $^{133}$Cs.

        Speaker: Dr. Thawatchai Itthipoonthanakorn (Office of Atoms for Peace)
      • 14:40
        Low-Dose Radiation Induced Oxidative Stress and Mitochondrial DNA Damage in Human Epithelial Lung Carcinoma A549 Cell Line 1h

        In recent years, increasing attention has been paid to the effects of low-dose radiation (LDR). Evaluation of mitochondrial DNA damage and mitochondrial dysfunction can be used to assess the biological effect of LDR. This study aims to investigate the mitochondrial DNA damage induced by LDR, and its relationship with reactive oxygen species (ROS) formation after exposure to LDR. Human epithelial lung carcinoma A549 cells were irradiated with 6 MV photon beam at 0.2 and 2 Gy for low- and high-dose radiation, respectively. For evaluation of the ROS formation after exposure to LDR, A549 cells were incubated with 5 mM of Glutathione as an antioxidant for 24 h prior irradiation. ROS formation and mitochondrial membrane potential were determined using fluorescent probes. Induction of mitochondrial DNA damage were evaluated by γ-H2AX foci. LDR induced an increase in mitochondrial DNA damage and ROS formation, as well as a decrease in mitochondrial membrane potential, in the A549 cells. By adding antioxidant, ROS level and mitochondrial DNA damage were decreased. We demonstrated a relationship between mitochondrial DNA damage and ROS formation after exposure to LDR, which might be responsible for understanding the biological effects of LDR in lung cancer treatment.

        Speaker: Dr. Thititip Tippayamontri (Department of Radiological Technology and Medical Physics, Faculty of Allied Health Sciences, Chulalongkorn University, Bangkok, Thailand)
      • 14:40
        Managing Exposure to Natural Sources: A Case Study of International Standards and New Challenges 1h

        Radiation protection in exposure to natural sources has been evolving for decades. In the last two decades, developments concerning exposure to NORM (naturally occurring radioactive materials) have resulted in progress towards achieving broad international consensus on managing exposure to NORM. However, the standards and regulatory approaches being adopted at the national level still need to be harmonized, especially in developing countries with limited regulatory resources. A large effort is underway at the national and international level to assess exposure to NORM and to develop strategies to address existing situations that give rise to exposures. The International Basic Safety Standards (BSS) provides numerical criteria for exemption and clearance for regulatory purposes as well as reference levels for control of exposure to radon in workplaces. From a global perspective, the new radiation protection challenges for natural sources include the harmonization of standards and regulatory approaches; the diverse nature of the industries and the need for an industry specific approach in determining radiation protection measures. The use of a graded approach in national regulations; radon in workplaces; the management of NORM residues and wastes are related issues. A summary is provided of the international standards and guidance on the control of exposure to natural sources.

        Speaker: Apisara Charoensri (Office of Atoms for Peace)
      • 14:40
        Method Validation for Determination of Some Rare-Earth Elements in Rice Using ICP-MS 1h

        In the present work, an inductively coupled plasma mass spectrometer operating in single quadrupole was performed for determination of some rare-earth elements including La, Sm, Eu, Tl, and U in rice. The samples were prepared by microwave digestion with nitric acid. The fortifications of rice samples at 3 levels were studied in order to check the accuracy of the proposed method. The experiment was performed under the internal standard method with the coefficient of determination higher than 0.9990. The average recoveries of all elements were higher than 92% with the standard deviation less than 4.5.

        Speaker: Dr. Chunyapuk Kukusamude (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:40
        Natural Rubber Block as Radiation Shielding for Medical Applications 1h

        In this study, a prototype of commercialized-style radiation shielding blocks based on natural rubber mixed with radiation shielding substance (i.e. lead and tungsten compound) was developed. It was found that the mechanical properties of these radiation shielding blocks (including hardness, tensile strength and elongation) were reduced with increasing of the amount of radiation shielding substance mixed in the radiation shielding blocks. However, the reduction of these mechanical properties does not affect the actual utilization since these radiation shielding blocks are normally not subjected to any strong force or pressure. In addition, the SEM images showed the uniform dispersion of radiation shielding substances in the rubber block texture. The results of gamma shielding block attenuation test using $^{137}$Cs (662 keV) source and $^{60}$Co (1,173, 1,332 keV) source showed that based on the gamma shielding block attenuation property and production capability, the most appropriate formula was a shielding block with 60% lead oxide, which was able to completely shield gamma radiation (> 99%). In comparison with a radiation shielding block with lead oxide, a radiation shielding block with tungsten oxide showed similar characteristics. Due to the higher price of tungsten oxide, natural rubber block with lead oxide is preferred. However, with an environmental concern, natural rubber block with tungsten oxide is preferred.

        Speaker: Dr. Orasa Onjun (Department of Science Service)
      • 14:40
        Neutron Scattering Study on Magnetism of Reduced Graphene Oxide (rGO) Prepared from Coconut Shells 1h

        Reduced graphene oxides (rGOs) provide an ideal playground to raise magnetism of intrinsically nonmagnetic graphene because of the existence of significant defects and functional groups on their layers. We have proposed a green synthesis method in preparing rGO from coconut shells as an effort to produce sufficient quantities of graphene to desired quality levels. The rGO has been synthesized from charcoal powders prepared from coconut shells by thermal reduction method at $400^\circ$C, $600^\circ$C, $800^\circ$C and $1000^\circ$C. It is found that the oxygen-containing groups reduces and the concentration of defects increases with an increase in the heating temperature, and hence contribute to the increment of magnetization. This finding confirms a theoretical prediction on defect induce magnetism in rGO, in which magnetic ordering preserves even up to room temperature. However, a mechanism by which magnetic moments at the defect sites communicate and an interaction among the defect-induced localized magnetic moments are still unclear. Neutron provide a sensitive microscopic probe with a possible high intensity to study a tiny magnetism on defect sites. In conjunction with muon-spin relaxation study, we intend to clarify a mechanism of defect induce localized magnetic moments in rGO.

        Speaker: Dr. Retno Asih (Institut Teknologi Sepuluh Nopember)
      • 14:40
        Nuclear and Radiological Facility Location Management System 1h

        To manage nuclear and radiation databases and also to enhance the nuclear and radiation safety regulation in Thailand, Nuclear and Radiological Facility Location Management System (NRFLMS) has been launched by the Office of Atoms for Peace (OAP) and Geo-Informatics and Space Technology Development Agency (GISTDA) since January 2017. The system consists of two main parts: Geographic Coordinates System and Nuclear and Radiological Emergency Notification System. The first system is able to show the location and neighborhood of the facilities as well as the details of radioactive materials including their isotopes, activities, utilization, risk assessments, license status and current radioactivity report. The second system has been developed for receiving radiation emergency notifications from those radiation facilities and eyewitnesses through the online application. The radiation emergencies that are able to be notified include conflagration, explosion, flooding at the facilities and damage or loss of radioactive sources etc. In the near future, NRFLMS can provide the essential data in the radiological emergency situation. Moreover, the system can also be useful to relevant national authorities as follows (1) to use data and lead to analysis the effects of radiation emergencies (2) to clarify types of emergency situations and radioactive materials and additional information (3) to support decision makers of national and local authorities to respond radiation emergencies efficiently.

        Keywords: Nuclear, Radiation, nuclear and radiation accident, regulations

        Speaker: Ms. Atchararat Chaimuanwong (Office of Atoms for Peace)
      • 14:40
        Precise Determination of U-235 and Ra-226 Photopeak Intensities in Naturally Occurring Radioactive Materials Using Optimization Subroutine Function 1h

        The need for determining the U-235/U-238 isotopic ratio in a naturally occurring radioactive material (NORM) is increasing to warn a leakage of uranium into the environment. During the process of seeking a non-destructive method of analyzing natural matrices for uranium isotopes U-235 and U-238, a major source of uncertainty was found to be the gamma-ray intensities. Ra-226 and U-235 are always found in the presence of each other in soil samples, and each has primary gammas whose energies differ by only 0.496 ± 0.014 keV. The least squares fitting method, using the MIGRAD function optimization subroutine in ROOT framework was implemented to obtain reliable values for the two photopeak intensities of Ra-226 and U-235. This framework was developed to examine the effect of increasing or decreasing the number of degrees of freedom in the fit on the confidence intervals of the fitted intensity parameters (heights of the two Gaussians). An IAEA U1GX natural uranium reference material known to be in secular equilibrium has been counted using an ORTEC HPGe detector with the sample in a Marinelli beaker geometry. It was found that the increased number of degrees of freedom approach (i.e., with a reduced number of free parameters) gives more accurate results for the photopeak intensities, with the determined ratio of U-235 to Ra-226 intensities having discrepancies in the range 0.27-2.8% from the expected ratio for natural uranium that is in secular equilibrium.

        Keywords: Uranium, HPGe, NORM, Environmental Radioactivity

        Speaker: Dr. Sy Minh Tuan Hoang (Institute of Fundamental and Applied Sciences, Duy Tan University)
      • 14:40
        Radioisotopes Production using (n,gamma) Reaction at PUSPATI TRIGA Reactor 1h

        The production of short-lived radioisotopes using neutron activation technique that employs (n, $\gamma$) reaction has been carried out at the 1MW PUSPATI TRIGA Reactor (RTP) with the thermal neutron flux $\sim 5 \times 10^{12}$ n cm$^2$s$^{-1}$. Several in-core locations are available to produce the radioisotopes for various medical and industrial applications such as Sm-153, Br-82, Au-198 and others related. Neutron activation technique was chosen due to the ability of target material absorbed the neutron to produce its isotope that cannot be chemically separated. This paper describes the use of a TRIGA reactor utilized a neutron activation technique to produce short-lived radioisotopes for various application in Malaysia.

        Speaker: Dr. Julia AbdulKarim (Malaysian Nuclear Agency)
      • 14:40
        Radon Concentration in Water in the Area of Doi-Saket district, Chiang Mai Province 1h

        The purpose of this study was to determine the radon concentration in water for consumption from Ban Pongkum region, Doi Saket district, Chiang Mai Province. All samples were collected from 9 sites including 7 well water samples, 1 tap water and 1 hot spring (spa pool). Radon concentration was measured with using RAD7 H2O. The results showed that the average of radon concentrations were 57.54±25.23 Bq/l, 60.90±14.17 Bq/l and 13.17±4.15 Bq/l in well, tap water and Doi-saket hot spring water (spa pool), respectively. Radon concentration in all samples were below the United States Environmental Protection Agency maximum contaminant level (U.S.EPA MCL) of 150 Bq/l. Annual effective dose resulting from radon in all samples ranged from 0.004 to 0.033 mSv/y which lower than ICRP recommended limit for members of the public of 1 mSv/y.

        Speaker: Dr. Tarika Thumvijit (Department of Radiologic Technology, Faculty of Associated Medical Sciences, Chiang Mai University, Chiang Mai, Thailand)
      • 14:40
        Risk Assessment to Natural Radiation Exposure from Soil Samples in The Jasmine Rice Cultivated Area, Roi Et Province, Thailand 1h

        Roi Et is one of the provinces with rice farming and exported to many countries around the world. In order to assess the radiation risk index from Jasmine rice cultivated soils, 175 samples in Roi Et province were measured using the gamma ray spectrometry technique for estimating the natural radioactivity levels. The specific activity of Ra-226, Th-232 and K-40 was found from 7.14 to 29.02 Bq/Kg with a mean value of 16.92 ± 1.16 Bq/Kg, 7.24 to 33.40 Bq/Kg with a mean value of 16.99 ± 2.24 Bq/Kg and 18.17 to 129.65 Bq/Kg with a mean value of 46.95 ± 6.79 Bq/Kg, respectively. However, the values of radium equivalent activity (Raeq), the external hazard index (Hex), the gamma-absorbed dose rate (D) and the annual effective dose equivalent (AEDEout) were also calculated to evaluate radiological hazards. The average values of Raeq, Hex, D and AEDEout were found to be 44.83 Bq/Kg, 0.12, 20.03 nGy/h and 0.02 mSv/y, respectively. From the results can demonstrate that the natural radioactivity from soil are not affect to population in the area, which the natural radioactivity levels and the radiation risk values of Roi Et soil samples are lower than the UNSCEAR values. Moreover, the data in this research can be used as the basis information of natural background radiation from soil in Roi Et and provides knowledge about the environmental radiation in daily life to people in the area.

        Speaker: Mr. Purit Quinram (Program of Physics, Faculty of Liberal Arts and Science, Roi Et Rajabhat University, Roi Et 45120, Thailand)
      • 14:40
        Simulation of Neutron-Shielding Materials Based on Metal Oxide/HDPE Composites Using a Monte Carlo Code of PHITS 1h

        Development of new and better neutron-shielding materials has become one of the most important issues in the requirements of radiation safety. In order to obtain estimated performances of the materials before actual production, simulations of neutron-shielding characteristics using well-proved methods are necessary. In this work, a Monte Carlo code of Particle and Heavy Ion Transport code System (PHITS) was used to simulate neutron-shielding properties of HDPE composites that were added with either B$_2$O$_3$, Sm$_2$O$_3$, Gd$_2$O$_3$, or CdO as a filler at various contents. The energy of the incoming neutrons was fixed at 0.025 eV and neutron beams were pointed at the right angle to the material’s surface. The results showed that Gd$_2$O$_3$/HDPE composites had the highest linear attenuation coefficient, implying the highest neutron-shielding ability, compared to other fillers at the same contents. Furthermore, the simulations showed that the values of linear attenuation coefficients of all fillers increased with increasing filler’s contents. Other information such as build-up factors, HVL, TVL, and backscattered ratios were also simulated and reported in this work. Information obtained from this work would not only give credible estimation of neutron-shielding properties of different fillers but also present alternative neutron-shielding fillers that could be used in lieu of a common B$_2$O$_3$ used in today’s products. We also encouraged further investigation of this work by comparing the simulated results with the actual experiment in order to obtain the accuracy of the simulation.

        Speaker: Dr. Kiadtisak Saenboonruang (Department of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University)
      • 14:40
        Structural and Magnetic Characterizations of Fe3O4/MWCNT/ZnO Nanocomposites for Radar Absorbing Material 1h

        The preparation of Fe$_3$O$_4$/MWCNT/ZnO nanocomposites was conducted by precipitation method. The nanocomposites were characterized by XRD resulting in two phases, i.e., magnetite and zinc oxide with spinel cubic and zinc hexagonal wurtzite structures. The FTIR characterization shows the functional group of C = C indicating the presence of MWCNT, Fe-O as characteristic of magnetite and Zn-O indicating the presence of zinc oxide in the composites. The particle size of the nanocomposites from SEM images results in 15.8 nm. Furthermore, the EDAX data confirms the results of the FTIR data indicating the presence of elements C, O, Fe, and Zn. Based on the data analysis of the magnetization data, the saturation magnetization value of the samples is 12.64 emu/gr with superparamagnetic character. The band gap value obtained from the UV-VIS analysis is 3.53 eV. Interestingly, the reflection loss value of the Fe$_3$O$_4$/MWCNT/ZnO is -22.57 dB with the absorption capacity of 78%, indicating that this material could be used as radar absorbing material (RAM). To complete the structural data, this research also requires advanced technique using neutron characterization to investigate the detailed nanostructures of the samples, i.e., particle and secondary sizes and distributions as well as from and structure factors, and also their aggregations.

        Keywords: Fe3O4, MWCNT, ZnO, RAM, Neutron

        Speaker: Ms. ST. Ulfawanti Intan Subadra (Department of Physics, Faculty of Mathematic and Sciences, Universitas Negeri Malang (UM), Jl. Semarang 5, Malang 65145, Indonesia)
      • 14:40
        Study of Biological Effects of Ionizing Radiation in Occupational Staff: Thailand 1h

        Office of Atoms for Peace (OAP), as the national regulatory body of Thailand, has initiated project on “Biological Effects of Ionizing Radiation in Public and Occupational Staff in Northern and Northeastern of Thailand. The objectives of the 5 years project are (1) to have completed database of radioactive materials and radioactive sources in Thailand (2) to validate method for measurement of ionizing radiation effects in public and medical staff, and (3) to access risk of staff in medical centers exposed to ionizing radiation. Briefly, dose-response curve of dicentric analysis assay from non-medical and medical staff with Co-60 sources has been established and demonstrated correlation of irradiated dose to human blood and frequency of aberrated chromosomes. It is found that all staff is safe at occupational doses. The results are in agreement with the previous study of irradiated Cs-137 and Co-60 from 0.1 Gy to 5 Gy performed by Department of Applied Radiation and Isotopes, Faculty of Science, Kasetsart University and Department of Pathology, Faculty of Medicine, Ramathibodi Hospital, Mahidol University and OAP, respectively. However, those dose-response curves should be further developed and validated for in vitro dose reconstruction in medical management in cases of radiological emergency in the country.
        Keywords: bio-dose, dosimetry, low dose

        Speakers: Natnalin Sastri (Office of Atoms for Peace), Ms. Usa Kullaprawithaya (Office of Atoms for Peace)
      • 14:40
        Study on Characteristic of Fricke Xylenol Gel Dosimeter : Application for Dose Evaluation in Radiotherapy 1h

        Accurate assessment of the radiation absorbed dose delivered to a tumor and different organs is potentially importance issue in clinical radiotherapy. The aim of this study is to evaluate the effectiveness of the Fricke xylenol gel dosimeter (FXG) to photon radiation. With this aim, the dose response of FXG and its behavior have been investigated. The sensitivity and accuracy of FXG were validated by irradiating FXG with gamma radiation at 1-200 Gy. To evaluate the long- and short-term consistency and reproducibility of FXG, the optical density was measured at 24, 48 and 120 h after irradiation. Light absorbance spectra were analyzed from 350-800 nm. A calibrated ionization chamber was used as a reference for dosimetry. Spectrophotometric measurement of FXG demonstrated the linearity up to 30 Gy, and then gradually reached a plateau. FXG showed a good stability over a period of 120 h after exposure to gamma radiation. FXG showed a high reproducibility which is in comparable to that obtained from the ionization chamber. The FXG showed high accuracy, sensitivity and reproducibility, thus enabling determination of absorbed dose from the clinical radiotherapy.

        Speaker: Ms. Phavinee Choosin (Office of Atoms for Peace)
      • 14:40
        Study on Neutron Energy Spectrum of Different Shielding Materials 1h

        Neutron energy spectrum measurement of four different shielding materials namely water, baryte colemanite, lead and paraffin were done using Radial Piercing Beamport at reactor TRIGA PUSPATI (RTP) in Malaysian Nuclear Agency. This beamport is installed with highly oriented pyrolytic graphite (HOPG) mosaic crystals as monocromator. The neutron energy of thermal neutron, fast neutron and gamma of these materials were measured using two types of neutron detectors. The first detector is a liquid scintillator of type NE213 for detecting neutrons with energies from 800 keV to 20 MeV. The second detector is the 3He gas that is suitable to detect spectrum of thermal neutrons up to 1.5 MeV neutrons. The effect of different type of materials and their arrangement/combination to the neutron energy spectrum will be studied to provide suitable arrangement for effective shielding for use in neutron beam installation at RTP .

        Speaker: Dr. Julie Andrianny Murshidi (Malaysian Nuclear Agency)
      • 14:40
        Survey of Radiation Dose and Dose Distribution from Computed Tomography: Phantom Study 1h

        This study aimed to use OSL dosimeter to measure the radiation dose and dose distribution from CT scan. OSL nanoDot® were placed on eyes, thyroids, breasts and lower abdomen of Rando phantom to measure the equivalent dose. OSL InLight® were attached to the column placed around the CT couch to measure the radiation distribution. The results showed that lower abdomen received the highest radiation doses when examined with the whole abdomen protocol (58.18 mSv). The organs outside the primary beam such as breasts, thyroids, and eyes received the radiation dose of 39.5 mSv, 2.22 mSv, and 0.59 mSv, respectively. The radiation distribution from CT scan showed that the radiation dose around gantry area (0.87 mSv) was higher than the couch area (0.02 mSv). Moreover, the radiation scattering at thyroid level was higher than gonad level. Radiation protection and ALARA principle can be applied to patients, staffs, and patient’s relatives to prevent any radiation incident.

        Speaker: Ms. Kemiga Kuepitak (Department of Radiology, Panyananthaphikkhu Chonprathan Medical Center, Srinakharinwirot University)
      • 14:40
        Survey of Radiation Dose in the Controlled and Supervised Area from CT and Fluoroscopy Room Using InLight® OSL Dosimeter 1h

        Once the ionizing radiation is used, routinely survey of radiation dose in the surrounding areas must be performed to ensure radiation safety. This study aimed to measure the radiation doses in the controlled and supervised areas from fluoroscopic room using environmental InLight® optically stimulated luminescent dosimeter (OSLD). The OSLDs were attached at 1.4 m height to the wall, door, and lead glass on the inside and outside of CT and fluoroscopic room to measure the radiation doses of the supervised and controlled area for 10 days. There were twelve and fourteen OSLDs attached position at CT and fluoroscopic room respectively. The results showed that the radiation dose rates of controlled area and supervised area of both x-ray room were 0.4 - 2.1 μSv/week which do not exceed the dose limits. The dose limits for controlled area and supervised area are 0.1 mSv/week and 0.02 mSv/week respectively. While the radiation dose rates in both CT and fluoroscopic room is high, the radiation worker is not recommended to stay in the room for a long time. It can be concluded that it is safe for radiation workers and the public to stay in the controlled area and supervised area. However, the radiation protection rules should be applied if the worker would like to stay in CT and fluoroscopic room during operation.

        Speakers: Dr. Vithit Pungkun (Office of Atoms for Peace), Ms. Panatsada Awikunprasert (Department of Physics, Faculty of Science, Khon Kaen University)
      • 14:40
        Synthesis and Characterization of Mn$_{0.25}$Fe$_{2.75}$O$_4$@PANI-CMC/PVA and Their Potential Application for Hyperthermia Therapy 1h

        The Mn$_{0.25}$Fe$_{2.75}$O$_4$@PANI particles have been successfully synthesized using in-situ polymerization method from iron sand. The characterizations were done using XRD, FTIR, VSM, TEM, VSM, and magneto-hyperthermia. The X-ray diffraction pattern showed that the Mn$_{0.25}$Fe$_{2.75}$O$_4$@PANI particles have a crystal size of 8.09 nm. The characterization results using VSM instruments showed that the Mn$_{0.25}$Fe$_{2.75}$O$_4$@PANI particles have superparamagnetic properties with a saturation magnetization of 2.85 emu/gr. The characterization results using magneto-hyperthermia instruments showed that the Mn$_{0.25}$Fe$_{2.75}$O$_4$@PANI particles have the potential for hyperthermia therapy with SAR about 1.81(C/mFe) W/gr. To complete the detailed structural characters, this research requires neutron characterization to investigate hierarchical nanostructures, i.e., form factor, structure factor, aggregation of the samples.

        Speaker: Ms. Nadiya Miftachul Chusna (Universitas Negeri Malang)
      • 14:40
        The Comparison of Air Kerma for Cs-137 and Co-60 Radiation Protection Calibrations in East Asia and Southeast Asia Region 1h

        The intercomparison programme for the national standard dosimetry laboratory should be initiated to support the activities for assuring the quality of measurement and to harmonize the standards for ionizing radiation metrology among the Asia-Pacific region. The accurate dose measurement, especially in developing countries, requires the adequate calibration facilities and quality assurance programme such as intercomparison programme to maintain their standards. The main objective of this research is to improve the quality audit system for supporting ISO/IEC 17025 accreditation system for Standard dosimetry laboratories in East Asia and Southeast Asia by the comparison programme of Air Kerma of Cs-137 and Co-60 using Optically Stimulated Luminesence Dosimeter (OSLD). There were three Primary Standard Dosimetery Laboratories and eight Secondary Standard Dosimetry Laboratories participated in the comparison. The requested irradiation dose for radiation protection level using Cs-137 and Co-60 were 5.00 mGy and 2.00 mGy respectively at 0 degree angle of incidence in term of Air Kerma. The results show a good agreement between the standard dosimetry laboratories in Asia-Pacific region within ±2 standard deviation above the mean using z-score test. For Cs-137 intercomparison, the maximum and minimum z-score were +1.80 and -1.15 respectively. For Co-60 intercomparison, the maximum and minimum z-score were +0.90 and -0.96 respectively.

        Speaker: Dr. Vithit Pungkun (Office of Atoms for Peace)
      • 14:40
        The Eye Lens Doses Assessment in Nuclear Medicine Using Correction Factor of Hp(3)/Hp(0.07) 1h

        Many reports presented the conversion coefficients from air kerma to Hp(3) especially for photons but rare information with dose conversion coefficients for beta radiation. The dose equivalent quantities for assessment of the eye lens dose for photons and beta radiation must be considered separately depended upon with penetrating radiation and low penetration depth. Recently, Behrens (Physikalisch-Technische Bundesanstalt (PTB)) presented the correction factors for the ISO rod phantom, a cylinder phantom, and the ICRU sphere for reference beta radiation fields of the BSS2 which calculated from Sr-90/Y-90. In this study, the eye lens doses assessment in nuclear medicine were evaluated by correction factor of Hp(3)/Hp(0.07) calibrated with Sr-90/Y-90 using a cylinder phantom and ISO rod phantom respectively. Hp(3) for radionuclides used for nuclear medicine such as I-131, Tc-99m and Ga-68, were calculated from correction factor for eye lens dose from small OSL dosimeters inserted in a cylinder phantom at depth 3 mm. The results showed that percentage differences between evaluated eye lens dose from the correction factor compared with Hp(0.07) evaluated from extremities dose were found to be not exceeding ± 15%.

        Speaker: Ms. Waraporn Sudchai (Thailand Institute of Nuclear Technology (Public Organization))
      • 14:40
        The Shielding Design of the Radio Frequency Cavity in the Storage Ring of the Thailand Synchrotron Radiation Light Source 1h

        The radio frequency (RF) cavity provides an electric field in direction of electron beam in the synchrotron radiation machine to accelerate electron beam or compensate electron beam energy loss. Thailand synchrotron radiation machine has installed a second RF systems in the straight ring since August 2016. The RF cavity of the system can provide a maximum accelerating voltage of 300 kV at its accelerating gap. During the commissioning of the cavity in August 2016, there was a high radiation detected outside the shielding wall of the storage ring. The local shielding was installed for the safe operation of RF cavity at 185 kV. There will be a new insertion device installed in storage ring during a machine shutdown period in August 2018. This insertion device requires an operation of the RF cavity higher than 185 kV, which increases the radiation. The new design of RF cavity local shielding will also be installed. The radiation from RF cavity was investigated and the local shielding was designed using Mote Carlo simulations. This paper presents a detailed investigation and design of a local shielding together with a radiation survey results after the installation of shielding.

        Speaker: Nawin Juntong (SLRI)
      • 14:40
        Wastewater Treatment by Dielectric Barrier Discharge Plasma 1h

        The influence of atmospheric non-thermal plasma on household wastewater is presented in this paper. A dielectric barrier discharge (DBD) plasma generator was designed for wastewater treatment. The DBD model was in vertical coaxial tube shape. 10-cm-diameter outer aluminum tube, bonded with 40 aluminum needles on the inner surface of the tube, was an anode, while the inner aluminum tube acting as a cathode was covered with the 2-mm-thick glass tube. Gap distance between the tip of needle and the outer surface of glass tube was 1 cm. 14.6 kHz AC high voltage source was supplied to the anode of plasma model for plasma generation at 0, 10, and 15 kV. Wastewater was released on the top of glass tube, passed DBD corona discharges generated between the needle tips and glass tube, flowed down to the storage tank, and pumped to the top of the model again. The treatment process was operated for 30 minutes with the water flowing rate of 2 min/L. From the experimental results, it shows that all plasma treatment conditions could improve the wastewater quality. The best results were found at 15 kV plasma-treated wastewater; the alkalinity, dissolved oxygen (DO), and conductivity were increased from the control group for 0.74, 0.73 mg/L, and 0.09 mS/cm, respectively. While biochemical oxygen demands (BOD), and chemical oxygen demand (COD) were decreased from the control group for 104 mg/L, and 2400 mg/l, respectively. Moreover, an offensive odor of wastewater could be reduced.

        Speakers: Mr. Khanit Matra (Srinakharinwirot University), Mr. Yottana Tanakarun (Srinakarinwirot University)
    • 15:50 17:00
      Oral 6: Block IX
      • 15:50
        Radiation Technologies for Industrial, Medical and Research Applications at ROSATOM 30m

        RUSATOM HEALTHCARE JSC (RHC) is responsible for development and promotion of advanced and innovative radiation technologies for industrial, medical and research applications within the State Corporation ROSATOM, Russian Federation. RHC’s major technologies include full-scale research, development and production of reactor and cyclotron radionuclides, full-cycle radiopharmaceutical production lines, manufacturing of various equipment such as cyclotrons with energies from 12 to 80 MeV or higher for specific scientific and research applications, auxiliary equipment for radiochemistry laboratories, diagnostic and therapeutic medical equipment based on radiation technologies, various types of radiation detection equipment, and equipment for industrial irradiation of food, agricultural, medical, and industrial products. The RHC’s leading role in manufacturing of radiation technology equipment and production of a wide range of radionuclides for medical and industrial applications is also supported by the possibility to develop and verify technologies on its own as well as various production sites within ROSATOM. For medical applications RHC supplies complete radiopharmaceutical production lines, including 12–80 MeV cyclotron with liquid and solid targets for production of PET and SPECT radionuclides, fully equipped radiochemistry and quality control laboratories, radiation monitoring equipment, and radiopharmaceutical production technologies in full compliance with GMP rules.

        Speaker: Oleg Ivanov (Rusatom Healthcare JSC, Russian Federation)
      • 16:20
        Error Detection Sensitivity Test Using Complex Errors on Three Patient-specific VMAT QA Systems 20m

        The purpose of this study was to investigate error detection sensitivity for three patient-specific VMAT QA systems (Delta4, EPID-based dosimetry, and Log file). Ten VMAT plans were randomly selected to perform error detection sensitivities. Artificial complex errors were introduced to the original plans then repeated the QA tests. These errors were simulated into three possible scenarios: uncertainty, miss-calibration, and worst-case scenario. For uncertainty scenario, the random errors (σ) of MLC at ± 2.0 mm and gantry angle at ± 2 degree were introduced. A systematic error of +2 MU, and random errors of MLC and gantry angle at ± 2.0 mm and ± 2.0 degree were applied as a miss-calibration scenario. For worst case scenario, errors were integrated between systematic and random variation of MLC and gantry angle at 2±0.5 mm and 2±0.5 degree, respectively. The dosimetric agreements between QA tests on original versus artificial error plans were determined using gamma analysis (criteria of 3%, 3 mm) to investigate error detection sensitivity. EPID had the most sensitivity to detect three possible scenarios with largest gamma pass-rate drop. Delta4 and Log file QA had similar sensitivity on error detection in worst-case scenario. EPID-based dosimetry showed the most sensitive QA tool to detect the realistic and complex errors in patient-specific VMAT QA.

        Speaker: Sangutid Thongsawad (Chulabhorn Royal Academy)
      • 16:40
        Development of EPID-based Dosimetry for FFF-beam Verification in Radiation Therapy 20m

        The purpose of this study was to develop electronics portal imaging device (EPID)-based dosimetry for flattening-filter-free (FFF) beam verification. All radiation measurements were performed with source to imager distances (SID) of 150 cm to reduce saturation effect. EPID images were converted to radiation absorbed dose in water at depth of 10 cm with our algorithm included three parameters (linearity of dose response with MU, beam profile correction, and scatter kernel). Image pixel values were scaled to dose (Gy) by using linearity of dose response with MU. Off-axis response differences between EPID and water were reduced with beam profile correction. To convert scatter dose distribution from EPID plane to water plane at depth of 10 cm, scatter kernel was applied to
        EPID images. The algorithm accuracy was validated with 36 fields of 10 VMAT plans by using gamma analysis comparing between our EPID-based dosimetry and plane dose distribution of treatment planning systems (TPS). Gamma passing rates (GPR) were determined with criteria of 2%, 2 mm. Mean of GPR was 97.74%, lowest was 93.60%, and the highest was 99.98 %. Our EPID based dosimetry showed good agreements with plane dose distribution in water. These results indicated that our EPID-based dosimetry can perform FFF-beam verification.

        Speaker: Mr. Thadpong Chanton (Naresuan University)
    • 15:50 17:00
      Oral 6: Block X
      • 15:50
        The DIII-D/EAST Joint Experiments on High Poloidal Beta Scenario Development Towards ITER and CFETR 30m

        Towards the ITER steady-state goal of Q=5, recent DIII-D/EAST joint experiments on high poloidal beta (βP) scenario development have demonstrated sustainment of excellent energy confinement quality (H98y2>1.5) via a large radius internal transport barrier (ITB) at high normalized beta (βN~3.5) and reactor-relevant q95~6.0 on DIII-D. This high normalized fusion performance ITB state with Greenwald density fraction near 100% and qmin≥3, is achieved with plasma toroidal rotation Vtor~0 at ρ≥0.6, a key result for a reactor where toroidal rotation is expected to be low. Experimental results also show that negative magnetic shear in the plasma core contributes to turbulence suppression and can compensate for reduced Shafranov shift to still access a large radius ITB and excellent confinement with low plasma rotation, consistent with results of gyrofluid transport simulations. In EAST, with the increased auxiliary heating and current drive capability, the operational regime has been extended (RF only: β_N ~1.5 and β_P~2.0; RF+NB : β_N ~2.0 and β_P~2.5). Using RF-only heating and current drive (lower hybrid LH, electron cyclotron EC, and ion cyclotron IC), EAST has achieved one hundred seconds steady state H-mode (H98y2~1.1) discharge at moderate βp~1.2 with actively cooled ITER-like mono-block tungsten divertor.

        Speaker: Dr. Juan Huang (ASIPP)
      • 16:20
        The Effect of Nuclear Equation of State on the Elliptic Flow in Heavy Ion Collision by Using Quantum Molecular Dynamics Model 20m

        This work concentrated on the effect of nuclear equation of state on the elliptic flow in heavy ion collision by using quantum molecular dynamics model (QMD). The elliptic flow of proton in $^{197}Au + ^{197}Au$ reaction at incident energy 0.25A GeV within the quantum molecular dynamics model was studied. The elliptic flow of proton ($v_{2}$) as a function of the centrality rapidity ($y_{0}$) was computed and compared with FOPI data. The calculations were performed with a soft/hard equation of state (EoS). The result of the elliptic flow of proton as a function of the centrality rapidity with $^{197}Au + ^{197}Au$ collision by using QMD model at the impact parameter from 0 to 0.25 and from 0.25 to 0.45 fm revealed that the equation of state can describe the behavior of matter in high density and high pressure. It was a soft EoS. With the theoretical result, the elliptic flow of proton is consistent with the experimental FOPI data.

        Speakers: Worrakarn Wangwon (Department of Physics, School of Science, University of Phayao), Ms. Suchanya Junsen (Department of Physics, School of Science, University of Phayao)
      • 16:40
        The Prediction of ${K^ - }p$ and ${K^ + }\bar p$ Bound States in $pp$ Collisions at 7 TeV 20m

        We analyze the yield of charged particles (${K^ + },{K^ - },p$ and ${\bar p}$) in $pp$ collisions at 7 TeV by using the PACIAE model and comparing with experimental data from ALICE. The prediction of ${K^ - }p$ and ${K^ + }\bar p$ bound states in $pp$ collisions at 7 TeV is calculated by using PACIAE+DCPC model. Using a realistic invariant mass of 1.405 GeV, we are predict the yields per event of ${K^ - }p$ and ${K^ + }\bar p$ bound states to be $3.530 \times {10^{ - 3}}$ and $3.270 \times {10^{ - 3}}$, respectively. The $\Lambda \left( {1405} \right)$ and it antiparticle may be produced at almost the same rate in $pp$ collisions at 7 TeV if the $\Lambda \left( {1405} \right)$ is a ${K^ - }p$ bound state. The total yield of ${K^ - }p$ and ${K^ + }\bar p$ is to be $6.80 \times {10^{ - 3}}$. There are no experimental data available for the yield of ${K^ - }p$ and ${K^ + }\bar p$. This research may provide a guide to future experiments.

        Speaker: Dr. Pornrad Srisawad (Department of Physics, Naresuan University, Phitsanulok 65000, Thailand)
    • 18:00 20:00
      Reception 2h
    • 09:00 10:10
      Oral 7: Block XI
      • 09:00
        Young Nuclear Scientist Award Presentation 30m
      • 09:30
        Fuel Performance Modeling and Sensitivity Study of Hard Spectrum BWR for Transuranic Waste Incineration 20m

        Hard spectrum boiling water reactor could serve as near-term alternative to sodium fast reactors for the application of transuranic waste incineration. To accurately analyze the fuel rod behavior of this reactor, modification of existing LWR fuel performance code is necessary because of significant deviation from typical operating condition of light water reactors. In this work, the physical phenomena at high temperature and high burnup conditions have been modeled and implemented in FRAPCON-3.5 EP. The fuel performance comparison between RBWR-TB2 and ABWR fuel rods suggest that because of high axial peaking factors and relatively flat power history, fuel temperature is significantly higher in fissile zones of the RBWR-TB2 leading to various undesirable effects such as excessive fission gas release and cladding deformation. Local fuel burnup in fissile zones of RBWR-TB2 is multiple times higher than that of ABWR leading to excessive fuel swelling, accelerated cladding oxidation, and PCMI at fissile-blanket interfaces. The sensitivity study on key design parameters indicates that using annular fuel geometry and more hypostoichiometric fuel (lower O/M ratio) could reduce fuel temperature at high burnup. For better resistance to cladding corrosion and PCMI, it is recommended to increase cladding thickness and decrease fuel density.

        Speaker: Dr. Yanin Sukjai (King Mongkut's University of Technology Thonburi)
      • 09:50
        Appearance of Gemstones and the Objective Assessment of Its Modification Caused by Irradiation and Heating Treatments. 20m

        We presented a method for the colorimetric assessment of cubic-shaped gemstones based on a fully controlled environment easily reproducible and its application to different specimens of quartz and topaz. The data regarding the color modification effect of E-beam irradiation and heating treatments in those minerals was described in the CIE L∗a∗b∗ perceptual color space. A general statistical approach to the visual characterization of the internal absorbance of gemstones in a low-dimensional space, evaluated its accuracy in terms of perceptual color difference, and applied it in the computational simulation of the treatments under study was introduced. The devices and model used in the present work has been proven to be applicable for gemstones’ absorbance characterization. A low-dimensional representation of the absorbance is feasible below the limits of human perception has been proven, although physically its modelling is clearly more complex. The introduction of the g-coefficients could serve as a two or three dimensional perceptual characterization of the material that is independent of the cut, hence more general than a color assessment. Our g-coefficient characterization to be perceptually accurate in the absorption effect modelling has been proven and is useful for color simulation of irradiation effect in gemstones under certain situations. With the additional parameter of refractive index and a geometrical model of the gemstone, the reflective effects can be also simulated visually, allowing computationally for accurate image simulations of the complex appearance of cut gemstones under any circumstances.

        Speaker: Dr. Pichayada Katemake (Department of Imaging and Printing Technology, Faculty of Science, Chulalongkorn University)
    • 10:10 10:40
      Coffee Break 30m
    • 10:40 11:30
      Oral 8: Block XII
      • 10:40
        A Preliminary Study on the Cultural Heritage Utilizing Neutron Beam at HANARO 30m

        Neutron beams can be used in a variety of research fields, and it is a very useful tool for studying cultural heritages that Non-invasive testing is essential. Cultural heritage is an important key to the study of ancient manufacturing techniques and their function. Among the many non-destructive tests, X-ray technology has come to be widely used for studies on the majority of archaeological objects. In general, an X-ray cannot provide detailed information inside a thick sample because of the attenuation characteristics. Neutrons, as opposed to X-rays, are the best type of probe for examining the interior of a thick sample. However, neutrons are used far less frequently in this field because of accessibility issues. HANARO is a powerful research reactor with thermal and cold neutron. Recently, preliminary studies have been carried out to apply neutron beams at HANARO to cultural heritage. Various neutron techniques were applied to preliminary studies, for example, neutron tomography, diffraction, residual stress, and so on. In this presentation, I would like to present the results of applying neutron beams to preliminary studies of cultural heritage, especially hidden relics.

        Speaker: TaeJoo Kim (Korea Atomic Energy Research Institute)
      • 11:10
        Effects of Zinc on Hydrogen Peroxide-Induced Corrosion of Stainless Steel at Temperatures up to 80$^o$C 20m

        Zinc injection has been widely applied for corrosion resistance of nuclear materials. The mechanism of the corrosion resistance, however, has not been completely understood. The protocol improvement is not possible without such information. In the present research, the effects of zinc on corrosion of SS 304 induced by H$_2$O$_2$ were studied at ambient pressure and temperatures up to 80$^o$C using a custom-made flow setup. Zinc ion in the form of zinc acetate at different concentrations was injected into the flow system composed of a glass hot cell where the SS 304 specimens were fully immersed in H$_2$O$_2$ solutions. XRD, XRF and SEM-EDX were used to examine the chemical composition and surface morphology of the specimens. The results indicated that pitting was the dominant form of corrosion found under the experimental conditions. Zinc ions tend to help mitigate corrosion of the material via playing a significant role in oxide formation on the steel surface.

        Speaker: Kotchaphan Kanjana (Thailand Institute of Nuclear Technology)
    • 11:30 13:00
      Lunch 1h 30m
    • 13:00 13:30
      Oral 9: Block XIII
      • 13:00
        Nuclear Scientist Award Presentation 30m
    • 13:30 14:00
      Closing Ceremony: Awards and Closing Ceremony
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