RSICC DATA LIBRARY DLC-205

1. NAME AND TITLE OF DATA LIBRARY

MCNPXDATA: Standard Neutron, Photon, Electron, and Proton Data Libraries for 
MCNPX 2.3.0 or 2.4.0.




2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS 

MAKXS: Prepares MCNP Cross-Section Libraries for MCNPX.




3. CONTRIBUTOR

Los Alamos National Laboratory, Los Alamos, New Mexico. 




4. HISTORICAL BACKGROUND AND INFORMATION

These cross-section libraries are released by the Diagnostics Applications Group, 
X-5, at Los Alamos National Laboratory for use with the MCNPX Monte Carlo code package. 
This release includes all of the X-5 distributed neutron data libraries, the photon 
libraries, and electron libraries that have been released as of September 2002. 
An updated XSDIR file and information and report files are also included. These data 
were previously released in DLC-105, DLC-181, DLC-189, and DLC-200.

Additions to the June 2002 D00205ALLCP02 release included the LA150U photonuclear 
data and LA150H proton data tables. A modification was made to correct a small error 
in the original release of LA150N. The ZAID for Pb-208 was changed from 82208.24c to 
82208.25c to differentiate from the earlier version. 

The September 2002 D00205ALLCP03 release includes all files in D00205ALLCP02 plus 
the EL03 electron data library. EL03 requires new functionality in MCNP4C or MCNPX 2.4.0. 
EL03 cannot be used with MCNP4B, MCNPX2.3.0 or earlier versions.

Several README files provide information regarding each data library of this release. 
Additional documentation for some of the individual libraries and example SPECS files 
for use with MAKXS are also provided. The XSDIR file is specific to this release and 
may not work with other packages. Currently LA150N is the default library for 
continuous-energy neutron transport. Additionally, MCPLIB02 is the default library 
for photon transport. The default electron library is EL in D00205ALLCP02 and is EL03 
in D00205ALLCP03. 




5. APPLICATION OF THE DATA

DLC-205/MCNPXDATA is for use with MCNPX and can be used with Version 4B, 4C and later 
of the MCNP transport code. Note the warning above regarding EL03 and earlier releases 
of MCNP. This library provides a comprehensive set of cross sections for a wide range 
of radiation transport applications using MCNPX.


6. SOURCE AND SCOPE OF DATA

The DLC-205/MCNPXDATA package is comprised of DLC-200/MCNPDATA, which was released 
for use with MCNP4C; plus the LA150N library of 42 high energy neutron data tables, 
LA150U photonuclear data for 12 isotopes, and LA150H proton data tables for 41 isotopes. 
The EL03 library is omitted from D00205ALLCP02 for MCNPX2.3.0, but it is included in 
D00205ALLCP03 for MCNPX 2.4.0. Electron tables with zaid numbers ending in .01e will 
work in MCNPX 2.3.0; others will not. In LA150N, the neutron energy is extended to 150 
MeV except for Be-9, which only goes to 100 MeV. This library typically extends ENDF/B-VI 
data from 20 MeV to 150 MeV; therefore, charged particle and recoil nuclei data will 
sometimes not be available below 20 MeV. Exceptions are noted in the MCNPX User's Manual. 
All standard neutron libraries used with MCNP4C (originally distributed in DLC-200 and 
now included in DLC-205) can be used with MCNPX 2.3.0; however, they will not contain 
emission data for charged particles or recoil nuclei; therefore, these products will 
not be tracked upon production. The new neutron libraries developed for use with MCNP4C 
will work with MCNPX 2.4.0, but some features specific to MCNP4C will not function in 
MCNPX 2.3.0. In particular, features related to probability tables and delayed neutrons 
will be ignored in MCNPX 2.3.0.

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: LA150N, ENDF60, RMCCS, RMCCSA, ENDF5U, ENDF5P, NEWXS, 
ENDF5MT*, MISC5XS**, ENDL85, KIDMAN, 100XS, URESA***, 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 was 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 four data libraries (URES, ENDF6DN, ENDF62MT, and ENDL92) were released 
in DLC-200. In the February 2001 update, URES was replaced with URESA. Please consult 
the README files and the more detailed documentation provided for descriptions of 
these libraries.




The LA150N neutron data library includes 42 isotopes: 1H, 2H, 9Be (100 MeV), natC, 
14N, 16O, 27Al, 28Si, 29Si, 30Si, 31P, natCa, 50Cr, 52Cr, 53Cr, 54Cr, 54Fe, 56Fe, 
57Fe, 58Ni, 60Ni, 61Ni, 62Ni, 64Ni, 63Cu, 65Cu, 93Nb, 182W, 183W, 184W, 186W, 196Hg, 
198Hg, 199Hg, 200Hg, 201Hg, 202Hg, 204Hg, 206Pb, 207Pb, 208Pb, 209Bi.

The LA150U photonuclear library includes 12 isotopes: 12C, 16O, 27Al, 28Si, 40Ca, 
56Fe, 63Cu, 181Ta, 184W, 206Pb, 207Pb, 208Pb.

LA150H Proton Data Library (updated 11/20/01) includes 41 isotopes: 1H, 2H, 12C, 
14N, 16O, 27Al, 28Si, 29Si, 30Si, 31P, 40Ca, 50Cr, 52Cr,53Cr, 54Cr, 54Fe, 56Fe, 57Fe, 
58Ni, 60Ni, 61Ni, 62Ni, 64Ni, 63Cu, 65Cu, 93Nb, 182W, 183W, 184W, 186W, 196Hg, 198Hg, 
199Hg, 200Hg, 201Hg, 202Hg, 204Hg, 206Pb, 207Pb, 208Pb, 209Bi.




7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

The MAKXS program is required if the user wants to translate the data into binary 
form. It is distributed with the MCNPX code. This translation saves disk space and 
cuts down on running time of MCNPX. Input to the executable MAKXS 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 read the comments in the MAKXS 
source for SPECS input specifications. 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

ASCII (Type 1); D00205/ALLCP/02 for use with MCNPX2.3.0 (June 2002).

ASCII (Type 1); D00205/ALLCP/03 for use with MCNPX2.4.0 (September 2002).

All data libraries are distributed in a GNU compressed Unix tar file. The data are 
in ASCII format and can be used with MCNPX on all computer platforms supported by 
the code. Note that the trailing "1" is no longer appended to file names for Type 1 
(ASCII) libraries.




9. TYPICAL RUNNING TIME

Run times vary according to problems and computer speed.




10. REFERENCES

When referring to the LA150 data, please cite the following publication: M. B. Chadwick, 
P. G. Young, S. Chiba, S. C. Frankle, G. M. Hale, H. G. Hughes, A. J. Koning, R. C. Little, 
R. E. MacFarlane, R. E. Prael, and L. S. Waters, "Cross Section Evaluations to 150 MeV 
for Accelerator-Driven Systems and Implementation in MCNPX," Nuclear Science and 
Engineering 131, Number 3 (March 1999) 293.




a.) The following documents are included in electronic (PDF) form with the package on 
the distribution CD in the DOC/D205DOC.PDF file:

Revised Appendix G for the MCNP4C manual (December 18, 2000).

R. C. Little, "Readme_LA150N," (July 2000, revised May 2002).

R. C. Little, "Readme_LA150H," (May 2002).

M. C. White, "Readme_LA150U," (June 2001).

S. C. Frankle and R. C. Little, "README_4C.TXT," 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).

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

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




b.) Additional documentation is distributed in electronic (PDF) format in the distribution 
tar file and will be extracted to the user's mcnpxdata/DOC subdirectory.

M. C. White, "Class 'u' ACE format Photonuclear Data," LANL Memo, file mcw-00-89.pdf 
(July 26, 2000).

M. C. White, "Release of the LA150U Photonuclear Data Library," LANL Memo, file 
mcw-00-87.pdf (Revised March 21, 2001).

M. C. White, "User Interface for Photonuclear Physics in MCNP(X)," LANL Memo, file 
mcw-00-88.pdf (Revised March 21, 2001).

M. C. White, "A Brief Primer for Simulating Photonuclear Interactions with MCNP(X),
" LANL Memo, file mcw-00-89.pdf (Revised March 21, 2001).

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). 




11. CONTENTS OF LIBRARY

Included are the documents referenced in 10.a and files described in Section 6. 
The ASCII libraries are distributed on CD-ROM in a GNU compressed Unix tar file. 
The data can be distributed on the same CD as the MCNPX 2.3.0 or MCNPX 2.4.0 code 
packages. WinZIP 8.0 or later is required to expand the files under Windows operating 
systems.




12. DATE OF ABSTRACT

August 2000, revised February 2001, May 2002, September 2002.

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