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

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

For fusion reactor nuclear analyses we produce new nuclear group constant sets, FUSION-F21.175 (neutron: 175 groups, : 42 groups, P5 approximation) and FUSION-F21.42 (neutron: 42 groups, : 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.