[3F08-10] Core Neutronics Evaluation

[3F10] Research and Development of RBWR for High Efficiency Transuranium Elements Burner

(1)Evaluation of Core Characteristics by Whole Core Neutron Transport Calculation

*Junichi Miwa¹, Yasunobu Nagaya², Masaya Ohtsuka¹ (1. Hitachi, 2. JAEA)

Keywords:BWR, TRU Burner, Whole Core Neutron Transport Calculation

Whole core Monte Carlo calculation system to be able to exclude the error of the multi group cross section calculation was constructed for RBWR (Resource-renewable Boiling Water Reactor) of high efficiency transuranium elements burner.The coupled neutronics / thermal hydraulics calculation and the depletion calculation were done.