Evaluation of large 3600 MWth sodium-cooled fast reactor OECD neutronic benchmarks

3600MWth級大型ナトリウム冷却高速炉の核特性ベンチマーク

Buiron, L.*; Rimpault, G*; Fontaine, B.*; Kim, T. K.*; Stauff, N. E.*; Taiwo, T. A.*; 山路 哲史*; Gulliford, J.*; Fridmann, E.*; Pataki, I.*; Keresztri, A.*; Tta, .*; 久語 輝彦 ; 杉野 和輝; 植松 眞理 マリアンヌ; Lin Tan, R.*; Kozlowski, T.*; Parisi, C.*; Ponomarev, A.*

Buiron, L.*; Rimpault, G*; Fontaine, B.*; Kim, T. K.*; Stauff, N. E.*; Taiwo, T. A.*; Yamaji, Akifumi*; Gulliford, J.*; Fridmann, E.*; Pataki, I.*; Keresztri, A.*; Tta, .*; Kugo, Teruhiko; Sugino, Kazuteru; Uematsu, Mari Mariannu; Lin Tan, R.*; Kozlowski, T.*; Parisi, C.*; Ponomarev, A.*

OECDの国際協力活動で実施中の大型ナトリウム冷却高速炉の核特性ベンチマークについて、複数の研究機関の参加者の評価結果を取りまとめた。反応度、同位体組成燃焼変化、反応度フィードバック、反応率分布について、異なる計算手法により評価された。参加者間の計算スキームの違いにかかわらず、燃焼組成、遅発中性子割合、ドップラー反応度係数、ナトリウムボイド反応度については、参加者間でよい一致を見た。しかしながら、臨界性に対しては、大きな差異が見られた。これは、計算手法の違いによるものではなく、使用した核データライブラリの違いによるものである。

Within the activities of the Working Party on Scientific Issues of Reactor Systems (WPRS) of the OECD, an international collaboration is ongoing on the neutronic analyses of several Generation-IV Sodium-cooled Fast Reactor (SFR) concepts. This paper summarizes the results obtained by participants from institutions of different countries (ANL, CEA, ENEA, HZDR, JAEA, CER, KIT, UIUC) for the large core numerical benchmarks. These results have been obtained using different calculation methods and analysis tools to estimate the core reactivity and isotopic composition evolution, neutronic feedbacks and power distribution. For the different core concepts analyzed, a satisfactory agreement was obtained between participants despite the different calculation schemes used. A good agreement was generally obtained when comparing compositions after burnup, the delayed neutron fraction, the Doppler coefficient, and the sodium void worth. However, some noticeable discrepancies between the k-effective values were observed and are explained in this paper. These are mostly due to the different neutronic libraries employed (JEFF3.1, ENDFB7.0 or JENDL-4.0) and to a lesser extent the calculations methods.