ZZ MCNPXS, Neutron, Photon Cross-Section Data Library from ENDF/B-V for MCNP-4B

1 - Description of program or function: Format: For use with the MCNP-4B transport code. Nuclides: H1, H2, H3, He3, He4, Li6, Li7, Be9, B10, B11, C, N14, N15, O16, O17, F19, Na23, Mg, Al27, Si, P31, S, S32, Cl, K, Ca, Sc45, Ti, V, Cr50, Cr52, Cr53, Cr54, Mn55, Fe54, Fe56, Fe57, Fe58, Co59, Ni58, Ni60, Ni61, Ni62, Ni64, Cu63, Cu65, Ga, Y89, Zr, Nb93, Mo, Tc99, Ag107, Ag109, In, I127, I129, Cs133, Cs134, Cs135, Cs136, Cs137, Ba138, Eu151, Eu153, Gd152, Gd154, Gd155, Gd156, Gd157, Gd158, Gd160, Ho165, Hf, Ta181, Ta182, W182, W183, W184, W186, Re185, Re187, Au197, Pb206, Pb207, Pb208, Bi209, Th230, Th232, Pa231, U232, U233, U234, U235, U236, U238, Np237, Np238, Np239, Pu236, Pu237, Pu238, Pu239, Pu240, Pu241, Pu242, Pu243, Pu244, Am241, Am242, Am243, Cm241, Cm242, Cm243, Cm244, Cm245, Cm246, Cm247, Cm248, Bk249, Cf249, Cf250, Cf251, Cf252. Origin: ENDF/B-V, LANL and ENDL85. These libraries are released by the Transport Methods Group, X-TM, at Los Alamos National Laboratory for use with the Monte Carlo code package CCC-0660/MCNP-4B. This release includes all of the X-TM supported neutron data libraries, the photon libraries MCPLIB1 and MCPLIB02, the electron library EL1, and updated XSDIR file, and an information file README. This release is intended to completely replace previous RSICC releases DLC-0105 and DLC-0181, as well as the cross sections previously included with CCC-0200/MCNP-4A, and will be updated as new libraries become available. The README information file provides information regarding each data library of this release. Additional documentation for some of the individual libraries and example SPECS files for use with MAKXSF are also provided. The XSDIR file is specific to this release and may not work with previous packages. Currently the neutron data library ENDF60 (based on ENDF/B-VI, up through and including release 2) is the default library for continuous-energy neutron transport. Additionally, the libraries MCPLIB02 and EL1 are the default libraries for photon and electron transport respectively. More information on the data libraries contained in this release is available in Appendix G of the MCNP-4B manual. DLC-0189/ZZ-MCNPXS is for use with Version 4B and later of the MCNP transport code. This data library provides a comprehensive set of cross sections for a wide range of radiation transport applications using the Monte Carlo code package CCC-0660/MCNP-4B. 4. Method of solution: A wide variety of continuous-energy, discrete, multigroup, thermal and dosimetry neutron data libraries are available in this release. The continuous-energy neutron data libraries available include: ENDF601, RMCCS1, RMCCSA1, ENDF5U1, ENDF5P1, NEWXS1, ENDF5MT1*, MISC5XS1**, ENDL851, KIDMAN1, and 100XS1. The discrete neutron data libraries include: NEWXSD1, DRMCCS1, DRE51. The multigroup neutron data library is MGXSNP1, and the thermal S(alpha, beta) libraries are TMCCS1 and THERXS1. The neutron dosimetry libraries are 531DOS1, 532DOS1, and LLLDOS1. The photon transport libraries are MCPLIB1 and MCPLIB02, and the electron library is EL1. The photon and electron data libraries contain data for elements having Z<95. The trailing '1' on the data library names generally indicate that the file is in ASCII, or type 1, format. Due to some platforms having a limitation of 8 characters for filenames, MCPLIB02 does not have the standard trailing '1' as part of its filename. * The data library ENDF5MT1 contains data previously available in the library EPRIXS, along with the U600K data library. ** The data library MISC5XS contains corrected data for ENDF/B-V based Zr as described below, and the libraries previously known as IRNAT, MISCXS, ARKRC, TM169, GDT2GP, and T2DDC. None of these data libraries have been previously distributed through RSICC. The ENDF/B-V Zr data has been corrected for five ZAID's from the libraries RMCCS, DRMCCS, ENDF5P, DRE5, and EPRIXS. Below is a summary of the changes that have been made for Zr: (Previous → Corrected) RMCCS 40000.51c → 40000.57c MISCD5XS 300 K; DRMCCS 40000.51d → 40000.57d MISCD5XS 300K; ENDF5P 40000.50c → 40000.56c MISCD5XS 300K; DRE5 40000.50d → 40000.56d MISCD5XS 300 K; EPRIXS 40000.53c → 40000.58c MISCD5XS 600 K. 2 - Restrictions on the complexity of the problem: The two files, PRPR and MAKXSF, are to be used only if the user wants to translate the data into binary form. They are distributed with the CCC-0660/MCNP-4B code package. This translation is recommended for saving disk space and cutting down on the running time of MCNP. Instructions for using PRPR and the source file for MAKXSF to produce the MAKXSF executable are included with the CCC-0660/MCNP-4B package. Input to the executable MAKXSF includes the SPECS files, the XSDIR1 file (nuclide data file directory) and the data libraries. The user should study the SPECS and XSDIR1 files and become familiar with the instructions for MAKXSF in the MCNP-4B manual. Some platforms have a restriction on the length of filenames, and the SPECS file may need to be appropriately edited