|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|DLC-0200/04||Linux-based PC,UNIX W.S.||Linux-based PC|
These cross-section libraries are released by the Diagnostics Applications Group, X-5, at Los Alamos National Laboratory for use with the MCNP Monte Carlo code package. This release includes all of the X-5 distributed neutron data libraries, the photon libraries MCPLIB1 and MCPLIB02, the electron libraries EL1 and EL03, an updated XSDIR file, and information files Readme.txt and Readme_endf60.txt. This release is intended to completely replace previous RSICC releases DLC-105, DLC-181, and DLC-189 as well as the cross sections previously included with CCC-200/MCNP4A, and will be updated as new libraries become available.
The README 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 EL03 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 MCNP4C manual.
ZZ-MCB-DLC200 contains the same cross section tables as the DLC-0200/03 package for the MCNP-4C code, except that the installation procedures are adapted to the MCB1C code system (NEA 1643/01).
DLC-200/MCNPDATA is for use with Version 4C 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-700/MCNP4C. See Appendix G of the MCNP report LA-13709-M for information on the libraries and how to select specific nuclides for use in MCNP.
SOURCE AND SCOPE OF DATA - 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: ENDF60, RMCCS, RMCCSA, ENDF5U, ENDF5P, NEWXS, ENDF5MT*, MISC5XS**, ENDL85, KIDMAN, 100XS, URES***, ENDF6DN***, ENDF62MT***, and ENDL92***. The discrete neutron data libraries include: NEWXSD, DRMCCS, and DRE5. The multigroup neutron data library is MGXSNP, and the thermal S(alpha, beta) libraries are TMCCS and THERXS. The neutron dosimetry libraries are 531DOS, 532DOS, and LLLDOS. The photon transport libraries are MCPLIB and MCPLIB02, and the electron libraries are EL and EL03***. The photon and electron data libraries contain data for elements having Z<95. The data libraries, as distributed, are in ASCII, or type 1, format.
* The data library ENDF5MT 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. 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:
40000.57c MISC5XS 300K
40000.57d MISC5XS 300K
40000.56c MISC5XS 300K
40000.56d MISC5XS 300K
40000.58c MISC5XS 600K
*** These five data libraries (URES, ENDF6DN, ENDF62MT, ENDL92, and EL03) are newly released in DLC-200. In the February 2001 update, URES was replaced with URESA. Please consult the README file and the more detailed documentation provided for descriptions of these libraries.
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 MCNP4C 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 MCNP4C package. Input to the executable MAKXSF includes the SPECS file, the XSDIR file (nuclide data file directory) and the data libraries. The user should study the SPECS and XSDIR files and become familiar with the instructions for MAKXSF in the MCNP4C manual. Some platforms have a restriction on the length of filenames, and the SPECS file may need to be appropriately edited.
|Package ID||Status date||Status|
|DLC-0200/04||30-AUG-2002||Tested at NEADB|
A. Adams, S. C. Frankle, and R. C. Little, "Revised Criticality Benchmarks for MCNP," Los Alamos National Laboratory memorandum (1996).
J. D. Court, R. C. Brockhoff, and J. S. Hendricks, "Lawrence Livermore Pulsed Sphere Benchmark Analysis of MCNP ENDF/B-VI," Los Alamos National Laboratory report LA-12885 (1994).
J. D. Court, J. S. Hendricks, and S. C. Frankle, "MCNP ENDF/B-VI Validation: Infinite Media Comparisons of ENDF/B-VI and ENDF/B-V," and errata, Los Alamos National Laboratory report LA-12887 (1994).
J. D. Court and J. S. Hendricks, "Benchmark Analysis of MCNP ENDF/B-VI Iron," Los Alamos National Laboratory report LA-12884 (1994).
S. C. Frankle, "Photon Production Assessment for the MCNP ENDF/B-VI Data Library," Los Alamos National Laboratory report LA-13093 (1995).
S. C. Frankle, "Cross-section and Reaction Nomenclature for MCNP Continuous- energy Libraries and DANTSYS Multigroup Libraries," Los Alamos National Laboratory memorandum XTM:SCF-96-313 (1996).
S. C. Frankle, "Experience with ENDF60 and QA of a Continuous-energy Library," Los Alamos National Laboratory memorandum XTM:SCF-96-363 (1996).
All data libraries are distributed in compressed mode. Files in the Unix tar file are in ASCII format and can be used with MCNP4C on all computer platforms supported by the code. Note that the trailing "1" was dropped from file names for Type 1 (ASCII) libraries. On the distribution CD, a self-extracting compressed file for Windows users contains both the MCNP4C code system with executables and cross-sections from MCNPDATA in binary format for PC users.
Contributed by:Radiation Safety Information Computational Center
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U. S. A.
Developed by:Los Alamos National Laboratory,
Los Alamos, New Mexico, U.S.A.
Contributed by:Department of Nuclear and Reactor Physics
Royal Institute of Technology
100 44 Stockholm
Keywords: group constants, libraries, multigroup, neutron cross sections, photon transport.