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Riyana, E. S.; 奥村 啓介; 坂本 雅洋; 松村 太伊知; 寺島 顕一; 神野 郁夫
Journal of Nuclear Science and Technology, 8 Pages, 2024/00
被引用回数：0 パーセンタイル：0.08(Nuclear Science & Technology)We investigated the possibility of estimating the effective neutron multiplication factor (
) of the fuel debris inside the canister and primary containment vessel (PCV) of Unit 2 of the Fukushima Daiichi Nuclear Power Station (1F) using remote gas-radioactivity measurement via simulation-based calculations. Our results demonstrate an almost linear correlation between and the 
Kr-to-
Xe activity ratio with respect to various fuel debris compositions. This correlation is maintained regardless of geometries such as the fuel debris canister and the PCV.
Riyana, E. S.; 奥村 啓介; 坂本 雅洋; 松村 太伊知; 寺島 顕一
Journal of Nuclear Science and Technology, 59(4), p.424 - 430, 2022/04
被引用回数：1 パーセンタイル：15.7(Nuclear Science & Technology)Modification of the Monte Carlo depletion calculation code OpenMC was performed to enable the depletion calculation of the subcritical neutron multiplying system. With the modified code, it became possible to evaluate the quantity of short half-life fission products from spontaneous and induced fissions in the subcritical system. As a preliminary study, it was applied to the fuel debris storage canister filled with nuclear materials and spontaneous fission nuclides. It was confirmed that the code could successfully provide a quantity of short half-life FPs over time and provide the relationship between the activity ratio of Kr-88 to Xe-135 and effective neutron multiplication factor of the canister.
奥村 啓介; 森 貴正; 中川 正幸; 金子 邦男*
Journal of Nuclear Science and Technology, 37(2), p.128 - 138, 2000/02
連続エネルギーモンテカルロ法による燃焼計算コードMVP-BURNを開発した。本コードの信頼性を確認するため、高転換軽水炉格子と可燃性毒物入りBWR燃料格子に対する燃焼計算ベンチマーク問題の解析を行った。その結果、主要な燃焼特性量に対して決定論的手法コードSRAC95の結果と良い一致を得た。強い非均質体系であっても特に問題となるような統計誤差伝播の影響は見られなかった。更に、JENDL-3.2ライブラリーを使用して、使用済み燃料の核種組成の解析を行い測定値との比較を行った。燃焼度34GWd/tにおける燃料組成の計算値は、核特性にはほとんど影響が無い
Np,
Pu,
Am及び
Cmを除いて、約10%以内で測定値と一致した。
Riyana, E. S.; 奥村 啓介; 坂本 雅洋; 松村 太伊知; 寺島 顕一
no journal, ,
Fuel debris has inherent neutron sources due to mostly spontaneous fissions. Therefore, the fuel debris inside a canister can be seen as a subcritical system with fixed neutron sources. A depletion calculation for the fuel debris inside the canister has been performed. The calculation results show the activity ratio of Kr-to-Xe in the fuel debris canister depending on the material compositions and effective neutron multiplication factor.
