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New nuclear data group constant sets for fusion reactor nuclear analyses based on FENDL-2.1

FENDL-2.1をベースにした核融合炉核解析用の新しい炉定数セット

今野 力; 太田 雅之; 権 セロム; 落合 謙太郎; 佐藤 聡

Konno, Chikara; Ota, Masayuki; Kwon, Saerom; Ochiai, Kentaro; Sato, Satoshi

核融合炉の核解析のために、FENDL-2.1からFusion-J3とFusion40形式の新しい2つの炉定数セットFUSION-F21.175 (中性子175群, $$gamma$$線42群, P5近似)とFUSION-F21.42 (中性子42群, $$gamma$$線21群, P5近似)をTRANSXコードで作成した。物質は、H-1, H-2, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-12, N-14, O-16, F-19, Na-23, Mg, Al-27, Si, P-31, S, K, Ca, Ti, V-51, Cr, Mn-55, Fe, Co, Ni, Cu, Zr, Nb-93, Mo, Cd, W, Pb, Bi-209, Cl, Ta-181, Sn及びGaの40。また、核発熱定数、損傷断面積、ヘリウム生成断面積等も整備した。これらの炉定数セットは自己遮蔽の補正がされていないことに注意する必要がある。これらの炉定数セットを用いたテスト計算を行い、問題がないことを確認した。

For fusion reactor nuclear analyses we produce new nuclear group constant sets, FUSION-F21.175 (neutron: 175 groups, $$gamma$$: 42 groups, P5 approximation) and FUSION-F21.42 (neutron: 42 groups, $$gamma$$: 21 groups, P5 approximation), similar with FUSION-J3 and FUSION-40 from FENDL-2.1 with the TRANSX code. The materials in these sets are H-1, H-2, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-12, N-14, O-16, F-19, Na-23, Mg, Al-27, Si, P-31, S, K, Ca, Ti, V-51, Cr, Mn-55, Fe, Co, Ni, Cu, Zr, Nb-93, Mo, Cd, W, Pb, Bi-209, Cl, Ta-181, Sn and Ga. It should be noted that the self-shielding effect is not corrected in these libraries. KERMA, DPA and gas production libraries are also prepared from the MATXS files with TRANSX. Several test calculations are carried out in order to validate these nuclear group constant sets. They suggest that these group constant sets have no problem.

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