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New nuclear data group constant sets for fusion reactor nuclear analyses based on JENDL-4.0 and FENDL-3.0

JENDL-4.0とFENDL-3.0をベースと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、JENDL-4.0とFENDL-3.0からFusion-J3と同様の新しい炉定数セットを作成した。物質は、$$^{1}$$H, $$^{2}$$H, $$^{3}$$He, $$^{4}$$He, $$^{6}$$Li, $$^{7}$$Li, $$^{9}$$Be, $$^{10}$$B, $$^{11}$$B, $$^{12}$$C, $$^{14}$$N, $$^{16}$$O, $$^{19}$$F, $$^{23}$$Na, Mg, $$^{27}$$Al, Si, $$^{31}$$P, S, K, Ca, Ti, $$^{51}$$V, Cr, $$^{55}$$Mn, Fe, Co, Ni, Cu, Zr, $$^{93}$$Nb, Mo, Cd, W, Pb, $$^{209}$$Bi, Cl, $$^{181}$$Ta, Sn及びGaの40。JENDL-4.0及びFENDL-3.0の炉定数セットFUSION-J40及びFUSION-F30(中性子175群、$$gamma$$線42群、P5近似)はNJOY99コードで作成したJENDL-4.0、FENDL-3.0のMATXSからTRANSXコードを用いて作成した。また、核発熱定数、損傷断面積、ヘリウム生成断面積等もMATXSファイルからTRANSXで整備した。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, we have produced new nuclear group constant sets similar with FUSION-J3 from JENDL-4.0 and FENDL-3.0. The materials in these sets are $$^{1}$$H, $$^{2}$$H, $$^{3}$$He, $$^{4}$$He, $$^{6}$$Li, $$^{7}$$Li, $$^{9}$$Be, $$^{10}$$B, $$^{11}$$B, $$^{12}$$C, $$^{14}$$N, $$^{16}$$O, $$^{19}$$F, $$^{23}$$Na, Mg, $$^{27}$$Al, Si, $$^{31}$$P, S, K, Ca, Ti, $$^{51}$$V, Cr, $$^{55}$$Mn, Fe, Co, Ni, Cu, Zr, $$^{93}$$Nb, Mo, Cd, W, Pb, $$^{209}$$Bi, Cl, $$^{181}$$Ta, Sn and Ga. The nuclear group constant sets of JENDL-4.0 and FENDL-3.0, FUSION-J40 and FUISON-F30 (neutron: 175 groups, $$gamma$$: 42 groups, P5 approximation), were produced from MATXS files of JENDL-4.0 and FENDL-3.0, which were newly processed with the NJOY99 code, with the TRANSX code. KERMA, DPA and gas production libraries were 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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