RSICC DATA LIBRARY DLC-200

1. NAME AND TITLE OF DATA LIBRARY

MCNPDATA: Standard Neutron, Photon, and Electron Data Libraries for MCNP4C.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

MAKXSF: Preparer of MCNP Cross-Section Libraries.

3. CONTRIBUTOR

Los Alamos National Laboratory, Los Alamos, New Mexico.

4. HISTORICAL BACKGROUND AND INFORMATION

These cross-section libraries were first released in April 2000 by the Diagnostics Applications Group, X-5, at Los Alamos National Laboratory for use with the MCNP4C Monte Carlo code package. The URESA file replaced URES in March 2001. No other changes were made to these data files since their April 2000 release. The MCNPDATA package was obsoleted from the RSICC collection when CCC-710/MCNP5 was released in May 2003, because updated data libraries are included in CCC-710. See the developers' website for information on newer data available in the MCNP5 code and data package: http://www-xdiv.lanl.gov/projects/data/nuclear/mcnpdata.html.

In February 2004, a GNU compressed Unix tar file containing ASCII cross sections was re-released by RSICC because users continue to request them for use with MCNP4C and MCNP4C-based codes. No changes to the data were made, and a WinZIP file containing MAKXS was included.

This release includes X-5 distributed neutron data libraries, photon libraries MCPLIB1 and MCPLIB02, electron libraries EL and EL03, XSDIR and information files. This release completely replaced older RSICC releases DLC-105, DLC-181, and DLC-189 as well as the cross sections previously included with CCC-200/MCNP4A.

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 other packages. 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, libraries MCPLIB02 and EL03 are the default libraries for photon and electron transport respectively. More information on data libraries contained in this release is available in Appendix G of the MCNP4C manual.

5. APPLICATION OF THE DATA

DLC-200/MCNPDATA is for use with Versions 4C and and 4C2 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. Newer MCNP cross sections from LANL are included in CCC-710/MCNP5.

6. 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:

(Previous) (Corrected)

RMCCS 40000.51c 40000.57c MISC5XS 300K

DRMCCS 40000.51d 40000.57d MISC5XS 300K

ENDF5P 40000.50c 40000.56c MISC5XS 300K

DRE5 40000.50d 40000.56d MISC5XS 300K

EPRIXS 40000.53c 40000.58c MISC5XS 600K

*** These five data libraries (URES, ENDF6DN, ENDF62MT, ENDL92, and EL03) were 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.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

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 and in this data package. This translation may save disk space and cut down on running time of MCNP. 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.

8. DATA FORMAT AND COMPUTER

(D00200/ALLCP/03) All data libraries are distributed in compressed mode. Files in the Unix tar file are in ASCII format and can be used with MCNP4C or 4C2 .

9. TYPICAL RUNNING TIME

Run times vary depending on processor speed and problem specifications.

10. REFERENCES

a.) The following documents are distributed in electronic (PDF) form with the package on CD in the DOC/D200DOC.PDF file:

R. C. Little, "ReadURES.txt" (February 2001).

S. C. Frankle and R. C. Little, "README," informal overview of the DLC-200: MCNPDATA package (April 2000).

S. C. Frankle, "README_ENDF60," informal overview of the ENDF60 neutron data library (April 2000).

J. S. Hendricks, S. C. Frankle, J. D. Court, "ENDF/B-VI Data for MCNP," and errata, Los Alamos National Laboratory report LA-12891 (1994).

H. G. Hughes, "Information on the MCPLIB02 Photon Library," Los Alamos National Laboratory memorandum X-6:HGH-93-77 (revised 1996).

R. C. Little, "Summary Documentation for the 100XS Neutron Cross Section Library," Los Alamos National Laboratory memorandum, XTM:95-259 and LA-UR-96- 24 (1995).

R. C. Little and R. E. Seamon, "Dosimetry/Activation Cross Sections for MCNP," Los Alamos National Laboratory memorandum (March 13, 1984).

R. C. Little, "Neutron and Photon Multigroup Data Tables for MCNP3B," Los Alamos National Laboratory memorandum X-6:RCL-87-225 (1987).

R. C. Little and R. E. MacFarlane, "ENDF/B-VI Neutron Library for MCNP with Probability Tables," Los Alamos National Laboratory Research Note XCI-RN(U)98-041, LA-UR-98-5718 (December 1998).

S. C. Frankle, "ENDF62MT, A Multi-temperature Neutron Library for MCNP (Rev.0), Los Alamos National Laboratory memorandum XTM:96-153 (April 1996).

C. Werner, "New Data Library for MCNP Delayed Neutron Capability," Los Alamos National Laboratory memorandum XCI:CJW-99-25 (April 1999).

K. J. Adams, "Electron Upgrade for MCNP4B," X-5-RN(U)-00-14 (May 25, 2000).

11. CONTENTS OF LIBRARY

Included are the documents referenced and the files described in Section 6. The files are distributed on CD-ROM in a GNU compressed Unix tar file. WinZIP 8.0 or newer is required to expand them under Windows.

12. DATE OF ABSTRACT

April 2000, revised July 2000, March 2001, February 2004.

KEYWORDS: NEUTRON CROSS SECTIONS; GAMMA-RAY CROSS SECTIONS; ELECTRON CROSS SECTIONS; PRODUCTION DATA; MULTIGROUP CROSS SECTIONS BASED ON ENDF/B; MCNP FORMAT; WORKSTATION; MICROCOMPUTER