ZZ WM-NRSM, Neutron and Gamma Group Cross-Section Library for Nuclear Rocket Shielding Calculations

Description of problem or function: - Master Library 1: Format: ANISN-W, DOT-IIW and APPROPOS. Number of groups: 52; Nuclides: Al, Be, B, B-10, Cd, C, Cr, Co, Cu, Gd, Au, H, In-115, Fe, Pb, Li, Li-6, Li-7, Mg, Mn, Mo, Ni, Nb, N, O, Si, Ta, Ti, W, U-235, U-238, Zr. Origin: Westinghouse Astro-nuclear Laboratory. Weighting spectrum: 1/E, flux and current spectra. - Master Library 2: Format: ANISN-W, DOT-IIW and APPROPOS. Number of groups: 52; Nuclides: Al, Be, B, B-10, Cd, C, Cr, Co, Cu, Gd, Au, H, In-115, Fe, Pb, Li, Li-6, Li-7, Mg, Mn, Mo, Ni, Nb, N, O, Si, Ta, Ti, W, U-235, U-238, Zr. Origin: Westinghouse Astro-nuclear Laboratory. Weighting spectrum: 1/E, flux and current spectra. - Master Library 3: Format: APPROPOS. Number of groups: 52; Nuclides: Al, Be, B, B-10, Cd, C, Cr, Co, Cu, Gd, Au, H, In-115, Fe, Pb, Li, Li-6, Li-7, Mg, Mn, Mo, Ni, Nb, N, O, Si, Ta, Ti, W, U-235, U-238, Zr. Origin: Westinghouse Astro-nuclear Laboratory. Weighting spectrum: 1/E, flux and current spectra. - Master Library 5: Format: KAP-VI, GAMLEG-W, MAC and SCAP. Number of groups: energy points in the range of 0.01 MeV to 20.0 MeV; Nuclides: H, He, Li, Be, B, C, N, O, Na, Mg, Al, Si, P, S, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Y, Zr, Nb, Mo, Ag, Cd, In, Sn, Cs, Ba, Sm, Gd, Dy, Y, Hf, Ta, W, Au, Hg, Pb, Po, Th, Pa, U, Np, Pu. Origin: Westinghouse Astro-nuclear Laboratory. - Basic set of nuclear data (Library 6): Format: ANISN-W and DOT-IIW. Number of groups: 52; Nuclides: H, Be, B, C, U-235, U-238, N, O, Mg, Al, Si, Cr, Mn, Fe Co, Ni, Cu, Zr, Mo, Ag, In, Cd, Gd, Pb, Nb, Ti, Ta, Li-6, Li-7, B-10 W, S. Origin: Master Libraries. Weighting spectrum: decided by user. WANL-MSFC Nuclear Rocket Shielding Data Generators GAMLEG-W, APPROPOS, NAGS, SATURN and Neutron and photon Cross Section Libraries 1-6. Applications of the Data: Transport codes which use the data are ANISN-W, KAP-VI, DOT-IIW, MAC and SCAP. The transport codes, also available from RSIC, the cross section processing codes, and the data libraries (both available in DLC-26) altogether comprise a comprehensive radiation analysis system for both preliminary parameter analysis and detailed design analysis. Scope of the Data: The compilation of neutron and photon cross section data for MSFC is in the form of five Master Library Data Sets and a set of basic nuclear data. Master Library No.1 contains 135 microscopic, transport corrected, neutron cross sections sets for 36 elements for use in the codes ANISN-W, DOT-IIW, and APPROPOS. These data are in a 52-group structure. Master Library No.2 contains 413 microscopic, PL (1 to 3) neutron cross section sets for 36 elements for use in the ANISN-W, DOT IIW, and APPROPOS codes. These data are also in a 52 energy group structure. Master Library No.3 contains 134 sets of reaction rate cross section data for use in the code APPROPOS. The data on Master Libraries No. 1, 2, and 3 are averaged over four representative, spatially dependent, neutron spectra obtained from WANL R-1 nuclear sub-system design work. These first three sets are obtained in a manner consistent with each other and with the nuclear and radiation analysis procedures used in the radiation analysis of reactors at the Westinghouse Astro-nuclear Laboratory (WANL). Master Library No.4 contains 510 microscopic, P1, gamma-ray cross section sets for 51 elements for use in the ANISN-W, DOT-IIW, and APPROPOS codes. These data which are in a 13 energy group structure, are averaged over a source spectra of prompt gamma ray energy emit- ted from the fission of 235-Uranium. This library is not distributed. It can be generated from Master Library No.5 (see below) using the code GAMLEG-W which is included in the distributed package. Master Library No.5 contains the pair-production and photo-electric gamma ray cross section data used in the KAP-VI, SCAP, MAP, and GAMLEG-W codes. Again, the data in sets 4 and 5 were obtained in a manner consistent with each other and with the radiation analysis procedures used in the radiation analysis of reactors at WANL. Finally, a basic set of nuclear data wa s generated for use in the complete package of codes