2020 Annual Meeting

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Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2I12-15] Development of Analysis Method & Code 2

Tue. Mar 17, 2020 3:50 PM - 4:55 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Hiroki Koike(MHI)

4:05 PM - 4:20 PM

[2I13] An Investigation on Improvement of the Core Neutronics Design Calculation Method for Advanced Fast Reactors (6)

Investigation on the improvement in power distribution evaluation

*Kazuteru Sugino1, Shigeo Ohki1 (1. JAEA)

Keywords:Fast reactor, Power distribution, Macro-cell, Re-homozenization, Reaction rate preservation, Discontinuity factors

炉心体系を模擬したマクロ格子モデルを用いて再均質化断面積及び反応率保存因子あるいは不連続因子を求め、炉心計算に適用することにより、次世代高速炉炉心の径方向出力分布評価の改善を図った。