Multi-group cross section library generation by FRENDY for fast reactor neutronics calculations

FRENDYを用いた高速炉核計算用多群断面積の作成

千葉 豪*; 山本 章夫*; 多田 健一   ; 遠藤 知弘*

Chiba, Go*; Yamamoto, Akio*; Tada, Kenichi; Endo, Tomohiro*

炉心解析コードCBZ用の多群断面積ライブラリを核データ処理コードFRENDYを用いて作成した。新しく作成した断面積ライブラリを用いて高速炉(MET-1000)を解析した。NJOY2016で作成した断面積ライブラリでの解析結果と比較した。その結果、両者の解析結果はよく一致することが分かり、FRENDYで適切に高速炉用の多群断面積ライブラリが生成できることを確認した。また、実効増倍率の微小な差異についても摂動論を用いてその要因を調査した。

The FRENDY nuclear data processing code has been used to generate multi-group cross section libraries for the CBZ reactor physics code system. The newly generated libraries have been applied to neutronics calculations of a fast reactor core MET-1000, and several neutronics parameters are calculated. Calculations with other libraries generated by NJOY2016 have been also conducted, and differences in obtained neutronics parameters between the FRENDY-based library and the NJOY-based library have been quantified. Generally reasonable agreement between them has been obtained, so it has been demonstrated that the multi-group libraries for fast reactor neutronics calculations can be generated successfully by FRENDY. Detailed investigation on the impact of the difference in the processing codes on k-effective has been also carried out with a help of the perturbation theory, and the causes of the differences have been identified.