[2B09-12] Analysis Method 1 (Burnup)

[2B11] Depletion calculation of subcritical system with consideration of spontaneous fission reaction

*Eka Sapta Riyana¹, Keisuke Okumura¹, Masahiro Sakamoto¹, Taichi Matsumura¹, Kenichi Terashima¹ (1. JAEA)

Keywords:subcritical system, burnup calculation, subcriticality, spontaneous fission product, Monte Carlo calculation

We enabled to consider the spontaneous fission reaction in subcritical neutron multiplying system by modifying the OpenMC depletion calculation code version 0.11. With the code, it is possible to estimate the quantity of short half-life fission products in the subcritical system. As a demonstration and fuel debris storage preliminary study, the code was applied to the fuel debris storage canister filled with nuclear materials and spontaneous fission nuclides. As a result, the ability was successfully shown to provide the information on short half-life fission products over time and to provide the relationship between the activity ratio of ⁸⁸Kr-to-¹³⁵Xe and effective neutron multiplication factor.