DLC-0177 ZZ-MATXS11.

ZZ-MATXS11.

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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.

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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.

NJOY91.91 was used to process this library derived from ENDF/B-VI. MATXS11 is an update of the ENDF/B-V derived DLC-116/MATXS6A library, which was added to the RSIC collection in December 1985.

BBC converted MATXS11 to binary in less than 2 minutes on a Sun Sparcstation 2.

The Fortran 77 program BBC is included in this package to convert the library to binary format for subsequent processing with the PSR-317/TRANSX2 code system to interface the MATXS cross-section libraries with nuclear transport codes for radiation transport calculations. Other functions of BBC include indexing MATXS libraries, and maintaining them by inserting, deleting, and extracting individual materials. Information on BBC, which was extracted from the TRANSX2 document, is given in APPENDIX A. This version of BBC is configured to run on Sun workstations.

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, USA

Developed by:   Los Alamos National Laboratory, New Mexico, USA