Speaker
Dr
Kanokrat TIYAPUN
(Thailand Institute of Nuclear Technology)
Description
The spent fuel storage of TRIGA reactor (TRR-1/M1) was designed. Detailed criticality safety analysis was conducted according to the basic safety standard and within the framework of the regulatory aspect. The Monte Carlo computer code (MCNP) was used for the detailed geometry modeling. Two types of fuel elements were considered for the calculation including 8.5 wt% and 20 wt% fuel elements. The critical number of the fuel elements was determined. The dependence of multiplication factor (keff) on the distance between the fuel elements in the rack (pitch) and the water density which varied from 0.01 g/cm3 to 1 g/cm3 were calculated. The MCNP results shown that the keff strongly depend on the lattice pitch, moderation effect and the water density. At present, there is limited experience in the safety management of spent fuel for research reactor. The strategy development and implementation of the integrated approach to management of the spent fuel from research reactor are important for the long term strategy of the ageing management program.
Country/ int. organization
Thailand Institute of Nuclear Technology
Primary author
Dr
Kanokrat TIYAPUN
(Thailand Institute of Nuclear Technology)
