DLC-0189: ZZ MCNPXS, Neutron, Photon Cross-Section Data Library from ENDF/B-V for MCNP-4B

Program-name Package-ID Status ZZ-MCNPXS DLC-0189/01 Obsolete ZZ-MCNPXS DLC-0189/02 Obsolete ZZ-MCNPXS DLC-0189/03 Tested ZZ-MCNPXS DLC-0189/04 Tested

Machines used: Package-ID Orig.Computer Test Computer DLC-0189/03 UNIX gen. W.S. DEC ALPHA W.S.,CRAY W.S.,HP W.S.,IBM RISC6000 WS,SGI W.S.,SUN W.S. DLC-0189/04 IBM PC PC Pentium II 400,PC Windows

3. DESCRIPTION OF PROGRAM OR FUNCTION -
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FORMAT: For use with the MCNP-4B transport code.
NUMBER OF GROUPS: --
NUCLIDES: H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C, N-14, N-15, O-16, O-17, F-19, Na-23, Mg, Al-27, Si, P-31, S, S-32, Cl, K, Ca, Sc-45, Ti, V, 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, Y-89, Zr, Nb-93, Mo, Tc-99, Ag-107, Ag-109, In, I-127, I-129, Cs-133, Cs-134, Cs-135, Cs-136, Cs-137, Ba-138, Eu-151, Eu-153, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158,
Gd-160, Ho-165, Hf, 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-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-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.
ORIGIN: ENDF/B-V, LANL and ENDL85.
WEIGHTING SPECTRUM: --
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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  300K
DRMCCS   40000.51d  -->  40000.57d  MISCD5XS  300K
ENDF5P   40000.50c  -->  40000.56c  MISCD5XS  300K
DRE5     40000.50d  -->  40000.56d  MISCD5XS  300K
EPRIXS   40000.53c  -->  40000.58c  MISCD5XS  600K

5. 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.

6. TYPICAL RUNNING TIME - Run times vary among computers.

DLC-0189/03:

TYPICAL RUNNING TIME - In the DEC Workstation equipped with a Alpha archit. processor of 500 MHz, a few minutes of elapsed time are required to perform the conversion of the complete set of data files.

DLC-0189/04:

TYPICAL RUNNING TIME - In the PC DELL Precision 410, equipped with a Pentium II at 400 MHz, a few dozens of minutes are required to perform the conversion of the complete set of data files.

7. UNUSUAL FEATURES OF THE PROGRAM -

9. STATUS
DLC-0189/01: 21-MAY-2002 Obsolete
DLC-0189/02: 21-MAY-2002 Obsolete
DLC-0189/03: 22-APR-1999 Tested at NEADB
DLC-0189/04: 22-APR-1999 Tested at NEADB

11. MACHINE REQUIREMENTS - All data libraries and files are in ASCII format and can be used with MCNP-4B on all computer platforms supported by the code. Prior to running with MCNP-4B, the XSDIR1 file will need to be renamed as XSDIR.

DLC-0189/03:

HARDWARE REQUIREMENTS - The diskspace required to hold the tar-compressed file is of about 170 MByte. After uncompression and extraction of the individual library files, about 466 MByte of diskspace are required to hold ALL the package files.

DLC-0189/04:

HARDWARE REQUIREMENTS - The diskspace required to hold the tar-compressed file is of about 170 MByte. After uncompression and extraction of the individual library files, about 466 MByte of diskspace are required to hold ALL the package files.

12. PROGRAMMING LANGUAGE(S) USED -
DLC-0189/03:
DLC-0189/04:

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED -

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHORS -
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.

16. MATERIAL AVAILABLE -
DLC-0189/03:
D189.LIS Listing of files
D189TAR0.Z Compressed Tar file
README.CD Information file
REAMDE.RSI RSICC information file
README (January 1997)
README_ENDF60 (January 1997)
LA-12891 (1994) and errata
Memorandum X-6:HGH-93-77 (revised 1996)
Memorandum XTM:95-259 and LA-UR-96-24 (95)
Dosimetry/Activation Cross Sec.(March 1984)
Memorandum X-6:RCL-87-225 (1987)
DLC-0189/04:
D189.LIS Listing of files
D189DOS0.EXE Self-extracting archive file
README.CD Information file
REAMDE.RSI RSICC information file
README (January 1997)
README_ENDF60 (January 1997)
LA-12891 (1994) and errata
Memorandum X-6:HGH-93-77 (revised 1996)
Memorandum XTM:95-259 and LA-UR-96-24 (95)
Dosimetry/Activation Cross Sec.(March 1984)
Memorandum X-6:RCL-87-225 (1987)

17. CATEGORIES  -

- J.  Gamma Heating and Shield Design
- Z.  Data.

Keywords: GROUP CONSTANTS, MULTIGROUP, NEUTRON CROSS SECTIONS, PHOTON TRANSPORT