ZZ ETOG-1-DATA, Cross-Section Library for Programs MUFT3, MUFT5, GAM1, GAM2 Generated from ENDF/B

1 - Description of problem or function: Format: MUFT4, MUFT5, GAM1, and GAM2. Number of groups: GAM1 → 68 groups, GAM2 → 99 groups, MUFT4,5 → 54 groups. Nuclides: H, D, Li-6, Li-7, Be-9, B-10, C-12, N-14, C-16, Mg, Al-27, Ti, V-51, Cr, Mn-55, Fe, Ni, Nb, Mo, Xe-135, Sm-149, Eu-151, Fu-153, Gd, Dy-164, Lu-175, Lu-176, Ta-181, Au-197, FP-U-233, U-234, U-235, FP-U-235, U-236, U-238, Np-237, Pu-238, Pu-239, FP-Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-243, Cm-244, Na-23, W-182, W-183, W-184, W-186, SFP-U-233, NFP-U-233, SFP-U-235, NFP-U-235, SFP-Pu-239, NFP-Pu-239. Origin: Brookhaven National Nuclear Data Center ENDF/B tapes 114 through 117. Weighting Spectrum: A 1/E weighting function joined to the fission spectrum was used. The data required for the creation of MUFT4, MUFT5, GAM1, and GAM2 libraries were generated from the Brookhaven National Nuclear Data Center ENDF/B tapes 114 through 117 by the ETOG1 program (NESC Abstract 437). 2 - Method of solution: The original ENDF/B data tapes 114, 115, and 116 received from the Brookhaven Center were altered. The CRECT program (NESC Abstract 384) was used to make corrections to mu bar, the average cosine of the scattering angle, xi, the logarithmic energy decrement, and gamma, the anisotropic Grueling- Goertzel parameter. Points were inserted into elastic scattering angular distribution tables so that anisotropy did not extend down to thermal energies, and the secondary distribution data for material numbers 1018 and 1021 were changed. The materials for which library data were generated are: 1001 H; 1019 Mn-55; 1037 Au-197; 1056 Am-241; 1003 D; 1020 Fe; 1042 U-233FP; 1057 Am-243; 1005 Li-6; 1021 Ni; 1043 U-234; 1058 Cm-244; 1006 Li-7; 1024 Nb; 1044 U-235; 1059 Na-23; 1007 Be-9; 1025 Mo; 1045 U-235FP; 1060 W-182; 1009 B-10; 1026 Xe-135; 1046 U-236; 1061 W-183; 1010 C-12; 1027 Sm-149; 1047 U-238; 1062 W-184; 1012 N-14; 1028 Eu-151; 1048 Np-237; 1063 W-186; 1013 C-16; 1029 Fu-153; 1050 Pu-238; 1066 U-233SFP; 1014 Mg; 1030 Gd; 1051 Pu-239; 1067 U-233NFP; 1015 Al-27; 1031 Dy-164; 1052 Pu-239FP; 1068 U-235SFP; 1016 Ti; 1032 Lu-175; 1053 Pu-240; 1069 U-235NFP; 1017 V51; 1033 Lu-176; 1054 Pu-241; 1070 Pu-239SFP; 1018 Cr; 1035 Ta-181; 1055 Pu-242; 1071 Pu-239NFP. 3 - Restrictions on the complexity of the problem: Library/No. of groups: GAM1/68, GAM2/99, MUFT4,5/54. A 1/E weighting function joined to the fission spectrum was used. A 1.0*107 value was used as the non-resonance potential scattering cross section per absorber atom. For MUFT libraries the 26. group was the lowest group number in the resonance region, the 25. group was the highest in the inelastic region