1. NAME AND TITLE OF DATA LIBRARY

MCNPXS: Standard Neutron, Photon, and Electron Data Libraries for MCNP4B.
 

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

PRPR: Fortran 77 pre-processor source.

MAKXSF: Preparer of MCNP Cross- Section Libraries.

These programs are distributed with the Monte Carlo code package CCC-660/MCNP4B.
 

3. CONTRIBUTOR

Los Alamos National Laboratory, Los Alamos, New Mexico.
 

4. HISTORICAL BACKGROUND AND INFORMATION

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- 660/MCNP4B. This release includes all of the X-TM supported neutron data libraries, the photon libraries MCPLIB1 and MCPLIB02, the electron library EL1, an updated XSDIR file, and an information file README. This release is intended to completely replace previous RSICC releases DLC-105 and DLC-181, as well as the cross sections previously included with CCC-200/MCNP4A, 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 MCNP4B manual.
 

5. APPLICATION OF THE DATA

DLC-189/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-660/MCNP4B.
 

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: 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 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
 

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 CCC- 660/MCNP4B 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-660/MCNP4B package. Input to the executable MAKXSF includes the SPECS file, 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 MCNP4B 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

All data libraries and files are in ASCII format and can be used with MCNP4B on all computer platforms supported by the code. Prior to running with MCNP4B, the XSDIR1 file will need to be renamed as XSDIR.
 

9. TYPICAL RUNNING TIME

Run times vary among computers.
 

10. REFERENCES

a. The following documents are distributed in electronic (PDF) form with the package:

S. C. Frankle, "README," informal overview of the DLC-189: MCNPXS package (January 1997).

S. C. Frankle, "README_ENDF60," informal overview of the ENDF60 neutron data library (January 1997).

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).
 

The following documentation are also distributed in electronic format (PDF) with the package:

A. 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).
 

b. Background information:

J. F. Briesmeister, Ed., "MCNP4B - A General Monte Carlo N-Particle Transport Code," LA-12625-M (1997).
 

11. CONTENTS OF LIBRARY

Included are the documents referenced in 10.a., and the files described in 6. The files are distributed in 2 format options: 1) CD-ROM in DOS and UNIX format; and 2) 4mm / 8mm tape in UNIX format.
 

12. DATE OF ABSTRACT

April 1997.
 

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