3. DESCRIPTION OF PROGRAM OR FUNCTION
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FORMAT: MATXS
NUMBER OF GROUPS: 80 neutron, 24 gamma-ray
NUCLIDES: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Ga, Y, Zr, Nb, Mo, Cd, In, Ba, Eu, Ho, Ta, W, Re, Au, Pb, Bi, Th, Pa, U, Np, Pu, Am, Cm, Cf.
ORIGIN: ENDF/B-VI
WEIGHTING SPECTRUM: Fast reactor or fusion blanket shape with a fusion peak at high energies and a 1/E + thermal Maxwellian extension at low energies.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% The following materials/nuclides (total of 105) are included in the library:
H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat, N-14, N-15, O-16, O-17, F-19, Na-23, Mg-nat, Mg-24, Al-27, Si-nat, P-31, S-32, S-nat, Cl-nat, Ar-40, K-nat, K-41, Ca-nat, Sc-45, Ti-nat, Ti-46, Ti-47, Ti-48, Ti-50, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Ga-nat, Y-89, Zr-nat, Nb-93, Mo-nat, Cd-nat, In-nat, Ba-138, Eu-151, Eu-153, Ho-165, Ta-181, Ta-182, W-182, W-183, W-184, W-186, Re-185, Re-187, Au-197, Pb-206, Pb-207, Pb-208, Bi-209, Th-230, Th-232, Pa-231, U-233, U-234, U-235, U-236, U-238, Np-237, Pu-236, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-244, Am-241, Am-242, Am-242m, Am-243, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Cf-250, Cf-252.
MATXS11 is useful for most high-energy calculations, including coupled neutron-photon-heating calculations in fusion blanket systems and the analysis of fast reactor cores.
The MATXS11 library uses 80 neutron groups and 24 photon groups and includes 105 materials from ENDF/B-VI (including changes through Release 2). The materials are given at up to 9temperatures ranging from 300 K to 4000 K with typically 5 to 8 background cross sections for each temperature.
The weight function had a fast reactor or fusion blanket shape with a fusion peak at high energies and a 1/E + thermal Maxwellian extension at low energies. The Legendre order for the scattering matrices is P5. Photon production, photon interaction, KERMA, damage, and all ENDF partial cross sections are included. Thermal upscatter is not included.