DLC-0176 ZZ-MATXS10.

ZZ-MATXS10.

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FORMAT: MATXS

NUMBER OF GROUPS: 30 neutron groups and 12 photon groups

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, Hf, Ta, W, Re, Au, Pb, Bi, Th, Pa, U, Np, Pu, Am, Cm, Bk, Cf, Es.

ORIGIN: ENDF/B-IV

WEIGHTING SPECTRUM: fusion + fission +1/E+ thermal Maxwellian shape

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The following materials/nuclides (total of 121) 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, Si-28, P-31, S-nat, S-32, 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-59, 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, Eu-155, Ho-165, Hf-nat, Ta-181, 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, Pa-233, U-232, U-233, U-234, U-235, U-236, U-238, Np-237, Np-238, Np-239, Pu-236, Pu-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-243, Pu-244, Am-241, Am-242, Am-242m, Am-243, Cm-241, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Bk-249, Cf-249, Cf-250, Cf-251, Cf-252, Cf-253, Es-253.

MATXS10 is useful for many high-energy calculations, including coupled neutron-photon-heating calculations in fusion systems, the analysis of fast critical assemblies like GODIVA, and some shielding calculations for which resonance self shielding effects are not too important. It has the advantage of being compact, and TRANSX2 and particle transport calculations run very fast with this library.

The MATXS10 library uses 30 neutron groups and 12 photon groups and includes 121 materials from ENDF/B-VI (including changes through Release 2). The materials are given at 300K without self shielding. The weight function had a fusion + fission + 1/E + thermal Maxwellian shape. The Legendre order for the scattering matrices is P4. 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. MATXS10 is an update of the ENDF/B-V derived DLC-115/MATXS5A library, which was added to the RSIC collection in December 1985.

BBC converted MATXS10 to binary in about 1 minute 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 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
                Los Alamos, New Mexico, USA