Abstract:
An upgrade of fuel management methodology for TRR-1/M1 is presented in this paper. The new methodology is to employ a more advanced code system called “SRAC” as a new fuel management tool for TRR-1/M1. The new methodology is executed in 2 steps, namely group cross section generation step and reactor core calculation step. The group cross section generation step of the new methodology utilizes hyperfine group structure capability of the SRAC system to create group cross sections into seven group structure. The reactor core calculation step of the new methodology is able to model hexagonal lattice of TRR-1/M1 using the generated cross sections. For verification purpose, the TRR-1/M1 core configuration number 1 and 2 are modeled by the new methodology in this paper. The results of the core excess reactivity of these core show good agreement with the operation data from operation log-book. In addition, the new methodology is able to provide the normalized power distribution of the reactor core which can not be obtained by the existing methodology. The new methodology is expected to be employed routinely as a new fuel management tool for TRR-1/M1 in the near future.