4-6 February 2019
Centara Grand at Central Ladprao
Asia/Bangkok timezone
Deadline for full paper revision: 21 May 2019.

Fuel Burnup Analysis and Fuel Management for TRIGA Mark III Research Reactor

5 Feb 2019, 14:40
1h 10m
Centara Grand at Central Ladprao

Centara Grand at Central Ladprao

Chatuchak, Bangkok 10900, Thailand
Poster Safety Poster 2

Speaker

Dr Kanokrat Tiyapun (Thailand Institute of Nuclear Technology)

Description

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.

Primary author

Dr Kanokrat Tiyapun (Thailand Institute of Nuclear Technology)

Co-author

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Paper