RSICC Home Page MCNP5/MCNPX

RSICC CODE PACKAGE CCC-740

The recent MCNP/MCNPX distribution (C740MNYCP06 & 07) did not contain updated data files used by MCNPX2.7 in the default data installer, although these files are present in the MCNPX2.7 source directory.  The missing data files named mollnix.tbl, gdr.dat, cinder.dat and delay_library.dat are used for photonuclear physics, delayed particle production and an update to the CEM physics model.  People who do not use these capabilities may not need the new files, but it is recommended everyone update to this latest release. Note: the updated data installer also contains a new photon library (mcplib05t) which improves scattering form factors in MCNPX2.7, but is not recommended as the default pending further testing.

 

1.         NAME AND TITLE

MCNP5/MCNPX:           Monte Carlo N–Particle Transport Code System Including MCNP5-1.60 and MCNPX-2.7.0 and Data Libraries.

The CCC-740 package contains MCNP5 1.60, MCNPX 2.7.0, and MCNPDATA. Abstracts follow.

MCNP5:     Monte Carlo N–Particle Transport Code System, MCNP5-1.60.

AUXILIARY PROGRAMS included in the distribution

MAKXSF:               Prepares MCNP cross-section libraries; now with Doppler broadening.

ONEGXS:               Create 1-group cross-sections with P0 or P1 scattering in ACE format.

RELATED DATA LIBRARY

MCNPDATA:          Standard Neutron, Photoatomic, Photonuclear, and Electron Data Libraries for MCNP5 and MCNPX.

Documentation on the data libraries may be found in Appendix G of the MCNP5 manual (Volume I) and on the web http://www-xdiv.lanl.gov/projects/data/nuclear/mcnpdata.html. A separate test library of cross sections is used for running regression sample problems, but the test library is not suitable for real problems.

2.         CONTRIBUTOR

Los Alamos National Laboratory, Los Alamos, New Mexico.

3.         CODING LANGUAGE AND COMPUTER          (See Section 11 below for more details.)

Package ID: C00740MNYCP08:    

Fortran 90 and C source code and executables for Windows PCs, Linux PCs, and MacOSX.

Package ID: C00740MNYCP09:   

Executables only (no source code) for Windows PCs, Linux PCs, Macintosh with MacOSX.

Export control regulations restrict the distribution of Fortran source code. If restrictions apply, RSICC will send the executable-only version. Please note that included MCNP5 executables run only on the machines listed below in section 9 of this abstract.

4.         NATURE OF PROBLEM SOLVED

MCNP5 is a general-purpose Monte Carlo N–Particle code that can be used for neutron, photon, electron, or coupled neutron/photon/electron transport, including the capability to calculate eigenvalues for critical systems. Some of the new features of MCNP5-1.60 include:

o        Adjoint-weighted Tallies for Point Kinetics Parameters

o        Mesh Tallies for Isotopic Reaction Rates

o        Greatly Increased Limits for Geometry, Tally, and Source Specifications

o        Web-based Documentation

o        Additional Test Suites for MCNP5

o        Modifications to the Regression Test Suite

o        Modifications to Criticality Test Suites

o        Modifications to Shielding Validation Suite

o        Enhancements to the merge_mctal and merge_meshtal Utilities

o        MCNP5-1.60 Build System and Directory Structure

o        Continue Runs May Use Different Number of Threads

o        RAND Card Allowed in Continue Run

o        Miscellaneous Enhancements/Changes

o        Numerous minor Bug Fixes

See the MCNP home page for up-to-date information http://mcnp.lanl.gov/ with a link to the MCNP Forum. For information on user experiences with MCNP, see the Electronic Notebook at http://rsicc.ornl.gov. Additional information posted by MCNP developers to the MCNP Forum can be viewed on the web in the MCNP5 electronic notebook in which the Forum entries are archived.

5.         METHOD OF SOLUTION

The MCNP5 code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and fourth-degree elliptical tori. Pointwise cross-section data are used. For neutrons, all reactions given in a particular cross-section evaluation (such as ENDF/B-VI) are accounted for. Thermal neutrons are described by both the free gas and S(α,β) models. For photons, the code accounts for incoherent and coherent scattering, the possibility of fluorescent emission after photoelectric absorption, and absorption in electron-positron pair production. Electron/positron transport processes account for angular deflection through multiple Coulomb scattering, collisional energy loss with optional straggling, and the production of secondary particles including K x-rays, knock-on and Auger electrons, bremsstrahlung, and annihilation gamma rays from positron annihilation at rest. Electron transport does not include the effects of external or self-induced electromagnetic fields. Photonuclear physics is available for a limited number of isotopes.

Important standard features that make MCNP very versatile and easy to use include a powerful general source, criticality source, and surface source; both geometry and output tally plotters; a rich collection of variance reduction techniques; a flexible tally structure; and an extensive collection of cross-section data. Energy ranges are from 10-11 to 20 MeV for neutrons with data up to 150 MeV for some nuclides, 1 keV to 1 GeV for electrons, and 1 keV to 100 GeV for photons.

6.         RESTRICTIONS OR LIMITATIONS

Energy ranges are noted above.

7.         TYPICAL RUNNING TIME

On a 2 GHz Pentium 4, compilation of MCNP5 takes about 3 minutes, and the 50 regression test cases run in about 2 minutes.

8.         COMPUTER HARDWARE REQUIREMENTS

MCNP5 is operable on PC's and on Macintosh (Intel-based) computers. Expanding and compiling the code system requires 500 MB, and the ASCII cross sections require ~11 GB of hard disk space. Up to 14 GB may be required during file expansion.

9.         COMPUTER SOFTWARE REQUIREMENTS

MCNP5 1.60 runs on PC's under Windows (Windows 7, Windows 2000, XP or Vista) or Linux and on Macintosh (Intel-based) computers with MacOSX. The code has improved support for newer Fortran 90 compilers. The gcc C compiler is used for all versions. The compilers supported are listed below.

Linux (32-bit and 64-bit):

o        g95 (0.9) mpi

o        gfortran (4.4.2) mpi

o        Intel (10.0, 11) omp, mpi

o        Portland (7.0-5, 9.0-3) omp, mpi

• Windows

o        Absoft (10.0)

o        Compaq (6.6B)

o        g95 (.92)

o        intel 11.1 (32-bit with plotting, 64-bit without plotting) omp, mpi

• Macintosh – Intel-based

o        Intel 10.1 (32-bit) & 11.1 (32- or 64-bit) mpi, omp

o        Absoft 11.0 mpi

o        gfortran 4.4.3

o        g95 (.92)

• Macintosh – PowerPC-based

o        No longer supported.

Included executables and reference templates for output and tally files used in the MCNP5 regression test suite were generated for Linux and Windows with the following compilers:

Windows: 32-Bit Pentium IV, Windows 2000 Professional SP4 with cygwin, Intel 9.1 f90, gcc

Linux: 64-bit AMD Opteron 2.0 GHz, Red Hat Linux 9, Intel 10.0.023 f90, gcc. Also included are MCNP5 Linux 32-bit executables – with and without OMP.

Mac: Intel-based and PowerPC-based executables are included.

Compilation of the MCNP5 source code in the C00740MNYCP08 distribution requires both Fortran 90 and ANSI C standard compilers. Dynamic storage allocation is available on all supported systems. Additional information may be posted to the MCNP Forum archives in the electronic notebook on the RSICC website.

The ‘omp’ notation after a compiler indicates that threading (also called “shared memory multiprocessing” or microtasking) can be used when building an MCNP5 executable. For computers having multi-core processors (e.g., Intel Core2 duo, Intel quad-core Xeon, etc.), MCNP5 should generally be compiled with the ‘omp’ option. Note that some compilers are not yet suitable for compiling a threaded version of MCNP5.

For compiling MCNP5 on Windows PCs, the Cygwin environment must first be installed. Cygwin is a collection of GNU-based Unix utilities which have been ported to Windows. The Cygwin environment may be obtained at no cost from the web site http://www.cygwin.com.

For plotting geometry, cross-sections, or results, X11 must be installed on your PC. An X-windows server is required to display the X11 graphics. Suggested servers include ReflectionX, Exceed, and XWin (Cygwin).

10.        REFERENCES

Included documentation in electronic format to be extracted to your hard drive:

Index file named ABOUT_MCNP5.htm, “Documentation for MCNP5 – 1.60.”

MCNP5 - 1.60 Release Notes, Los Alamos National Laboratory report LA-UR-10-06235.

MCNP5 - 1.60 Feature Enhancements & Manual Clarifications, Los Alamos National Laboratory report LA-UR-10-06217.

Verification of MCNP5 - 1.60, Los Alamos National Laboratory report LA-UR-10-05611.

X-5 Monte Carlo Team, MCNP–A General Monte Carlo N-Particle Transport Code, Version 5 - Vol. I: Overview and Theory, Los Alamos National Laboratory report LA-UR-03-1987 [file MCNP5_manual_VOL_I.pdf] (April 2003, revised 2/1/2008).

X-5 Monte Carlo Team, MCNP–A General Monte Carlo N-Particle Transport Code, Version 5 - Volume II: User’s Guide, Los Alamos National Laboratory report LA-CP-03-0245 [file MCNP5_manual_VOL_II.pdf] (April 2003, revised 2/1/2008).

X-5 Monte Carlo Team, MCNP–A General Monte Carlo N-Particle Transport Code, Version 5 - Volume III: Developer’s Guide, Los Alamos National Laboratory report LA-CP-03-0284 [file MCNP5_manual_VOL_III.pdf] (April 2003, revised 2/1/2008). [Volume III is omitted from the executable-only distribution.]

README.txt & MCNP5_Install_Guide.pdf, “Installing and Running MCNP on Various Systems,” App. C of Los Alamos National Laboratory report LA-CP-03-0284 (Revised 2/1/2008).

MCNP5 Utility Programs, Los Alamos National Laboratory report LA-UR-08-0306.

Criticality Calculations with MCNP5: A Primer, 3nd Edition, Los Alamos National Laboratory report LA-09-00380 (2009).

Many more reference documents (~145 total) on MCNP are included in the “docfiles” subdirectory on topics such as: Monte Carlo methods, random numbers, criticality calculations, variance reduction, medical physics, verification & validation, detectors, parallel calculations, etc.

11.        CONTENTS OF CODE PACKAGE

The MCNP/MCNPX package is distributed on a single DVD that can be read on Windows, Linux or Mac. The executable-only package C00740MNYCP09 includes MCNP5 and makxsf executables for PC Windows, PC Linux, and Mac OSX; a Windows executable for VISED; MCNPDATA; test problems and the referenced electronic documents listed in Section 10 above except for LA-CP-03-0284 Volume III.

The C00740MNYCP08 package includes the entire C00740MNYCP09 distribution plus source codes, makefiles, build scripts, and LA-CP-03-0284 Volume III. Additionally, this distribution includes several utility programs that provide support for a user's workflow in carrying out MCNP5 calculations:  makxsf, mcnp_pstudy, merge_mctal, merge_meshtal, onegxs, MCNP5 random number generator, event-log analyzer.

12.        DATE OF ABSTRACT

October 2008, revised February 2009, September 2010; June 2011

KEYWORDS:       COMPLEX GEOMETRY; COUPLED; CROSS SECTIONS; ELECTRON; GAMMA-RAY; MONTE CARLO; NEUTRON


RSICC CODE PACKAGE CCC-740

1.         NAME AND TITLE

MCNP5/MCNPX:           Monte Carlo N–Particle Transport Code System Including MCNP5-1.60 and MCNPX 2.7.0 and Data Libraries.

The CCC-740 package contains MCNP5-1.60, MCNPX-2.7.0, and MCNPDATA.

MCNPX:     Monte Carlo All-Particle Transport Code System, MCNPX 2.7.0.

RELATED DATA LIBRARIES 

MCNPDATA:          Standard Neutron, Photoatomic, Photonuclear, Electron, and Proton Data Libraries for MCNP5 and MCNPX.

AUXILIARY PROGRAMS included in the distribution

GRIDCONV:           Converts output of mesh and radiography tallies to input for external graphics programs.

HTAPE3X:              Postprocessor for MCNPX HISTP output.

MAKXSF:               Prepares MCNPX Cross-Section Libraries.

HCNV and TRX:      Convert LAHET ASCII data to binary.

XSEX3:                   Analyzes a HISTP history file and generates double-differential particle production cross sections for primary beam interactions.

Documentation on the data libraries may be found in Appendix G of the MCNP5 manual (Volume I) and on the web http://www-xdiv.lanl.gov/projects/data/nuclear/mcnpdata.html. A separate test library of cross sections is used for running regression sample problems, but the test library is not suitable for real problems.

Running MCNPX requires the included MCNPDATA continuous energy cross-section data. This library distribution includes the standard MCNP libraries, along with the ENDF70PROT proton data tables for 47 isotopes and the ASCII data files mentioned above. It should be noted that many of the high-energy libraries (ENDF70x, ENDF70PROT, etc.) contain emission data for light ions (i.e., Z=1-2), and in many cases only above 20 MeV (details are provided in the MCNPX User’s Manual).

2.         CONTRIBUTOR

Los Alamos National Laboratory, Los Alamos, New Mexico.

3.         CODING LANGUAGE AND COMPUTER          (See Section 11 below for more details.)

Fortran 90 and C and exes; Windows & Linux PCs, Sun; IBM; DEC (C00740MNYCP08).

Executables (no source code) for Windows PCs, Linux PCs (C00740MNYCP09).

Export control regulations restrict the distribution of Fortran source code. If restrictions apply, RSICC will send the executable-only version. Please note that included MCNPX executables run only on the machines listed below in section 9 of this abstract.

4.         NATURE OF PROBLEM SOLVED

MCNPX (MCNP eXtended) is a Fortran90 (F90) Monte Carlo radiation transport computer code that transports many particles over a broad range of energies. It is a superset of MCNP4C3 and has many capabilities beyond MCNP4C3. MCNPX is a production computer code that models the interaction of radiation with matter. New capabilities and enhancements of MCNPX 2.7.0 beyond MCNPX 2.6.0 are listed below. For details, see LA-UR-11-2295.pdf posted on the MCNPX website http://mcnpx.lanl.gov/.

·         Tally tagging;

·         CEM 3.02 upgrade;

·         Plot appearance upgrades;

·         Embedded sources;

·         Stopping power energy table control;

·         Cyclic time bins;

·         Focused beam sources;

·         PTRAC coincidence option;

·         LLNL fission multiplicity;

·         Arithmetic MCPLOT options;

·         Receiver-operator characterization (ROC) tally option;

·         Pulse-height light tally:  triple and quadruple coincidences;

·         Time-dependent F8 tallies using the pulse-height light option;

·         LAQGSM 3.03 upgrade.

MCNPXTM is a general purpose Monte Carlo radiation transport code that tracks nearly all particles at nearly all energies. The official release date of MCNPX 2.7.0 is April 18, 2011. MCNPX began in 1994 as a code-merger project of MCNP 4B and LAHET 2.8. It was first released to the public in 1999 as version 2.1.5. In 2002, MCNPX was upgraded to MCNP 4C, converted to Fortran 90, enhanced with 12 new features, and released to the public as version 2.4.0. The release of version 2.7.0 includes many new features described in the “MCNPX Extensions Version 2.7.0” document which is provided with the MCNPX distribution. The depletion/burnup capability is based on CINDER90 and MonteBurns. MCNPX depletion is a linked process involving steady-state flux calculations in MCNPX and nuclide depletion calculations in CINDER90. Currently, the depletion/burnup/transmutation capability is limited to criticality (KCODE) problems. Physics improvements include new versions of Cascade-Exciton Model (CEM) and Los Alamos Quark-Gluon String Model (LAQGSM) event generator, and a substantial upgrade to fission multiplicities. Current physics modules include the Bertini and ISABEL models taken from the LAHET Code System (LCS), CEM 03, and INCL4. Many new tally source and variance-reduction options have been developed. MCNPX is released with libraries for neutrons, photons, electrons, protons and photonuclear interactions. In addition, variance reduction schemes (such as secondary particle biasing), and new tallies have been created specific to the intermediate and high energy physics ranges. The ‘mesh’ and ‘radiography’ tallies were included for 2- and 3-dimensional imaging purposes. Energy deposition received a substantial reworking based on the demands of charged-particle high-energy physics. An auxiliary program, GRIDCONV, converts the mesh and radiography tally as well as standard MCTAL-file results for viewing by independent graphics packages. The code may be run in parallel at all energies via PVM or MPI. Information about MCNPX development can be found on the web site http://mcnpx.lanl.gov/.

5.         METHOD OF SOLUTION

All capabilities of MCNP4C3 have been retained. Consult the MCNPX User’s Manual for applicability to high energy applications.

6.         RESTRICTIONS OR LIMITATIONS

All standard MCNP neutron libraries over their stated ranges (~0-20 MeV).

Neutrons in the ENDF70x libraries from 0.0 - 150.0 MeV in tabular range.

Neutrons from 1.0 MeV in the physics model regime.

Photons from 1 keV - 100 GeV.

Photonuclear interactions from 1.0 to 150.0 MeV in tabular range.

Photonuclear interactions from 1.0 MeV in the CEM physics model.

Electrons from 1 keV - 1 GeV.

Protons from 1.0 to 150.0 MeV in tabular range for 47 isotopes.

Protons from 1.0 MeV in the physics model regime.

Pions, muons, and kaons are treated only by physics models.

Light ions from 1 MeV/nucleon in the physics model regime.

Heavy ions from 3 MeV/nucleon in the LAQGSM physics model.

7.         TYPICAL RUNNING TIME

Runtimes vary depending on computer speed and problem parameters. On a 2 GHz Pentium 4, compilation of MCNPX takes about 5 minutes. Test cases run in about 5 minutes.

8.         COMPUTER HARDWARE REQUIREMENTS

MCNPX runs under Unix, Linux, and Windows operating systems and has been implemented on various 32-bit and 64-bit workstations and personal computers. The compiled version of the code tends to run ~8 Mbytes. Dynamic allocation makes memory demands variable on all platforms.

9.         COMPUTER SOFTWARE REQUIREMENTS

C and Fortran 90 compilers are required to compile. The GNU make utility is required to build the system on Unix and Linux platforms. The GNU make.exe utility is included for Windows users. The only graphics support for this release is X11 http://www.x.org/. This is a Fortran 90 version of MCNPX which uses standard F90 allocation schemes for dynamic variables on all platforms. The package includes MCNPX 2.7.0 executables created by the LANL developers for the systems listed below. Each of these files contains precompiled executables and corresponding binary data libraries for bertin and phtlib.

·         Win32_Seq.zip: Windows executables, with Intel 11.1 on a 32-bit XP OS.

·         Win32_I8.zip: Windows 8-byte integer executables, with Intel 11.1 on a 32-bit XP OS.

·         Win32_MPI.zip: Windows MPICH-2 executables, with Intel 11.1 on a 32-bit XP OS.

·         Win32_MPI_I8.zip: Windows 8-byte integer MPICH-2 executables, with Intel 11.1 on a 32-bit XP OS.

·         Win64_Seq.zip: Windows executables, with Intel 11.1 on a 64-bit Windows 7 OS.

·         Win64_I8.zip: Windows 8-byte integer executables, with Intel 11.1 on a 64-bit Windows 7 OS.

·         Win64_MPI.zip: Windows MPICH-2 executables, with Intel 11.1 on a 64-bit Windows 7 OS.

·         Win64_MPI_I8.zip: Windows 8-byte integer MPICH-2 executables, with Intel 11.1 on a 64-bit Windows 7 OS.

·         Linux_Intel.tar.gz: Linux executables, with INTEL 10.1 on a 64-bit GNU/Linux OS.

·         Linux_PGI.tar.gz: Linux executables, with PGI 10.2 on a 64-bit GNU/Linux OS.

10.        REFERENCES

a)         included in documentation

D. B. Pelowitz, ed., MCNPX User's Manual, Version 2.7.0, Los Alamos National Laboratory report LA-CP-11-00438 (April 2011).

J. S. Hendricks, et al., MCNPX 2.7.0 Extensions, Los Alamos National Laboratory report LA-UR-11-02295 (April 2011).

A. L. Schwarz , R. A. Schwarz, and L. L. Carter, “MCNP/MCNPX Visual Editor Computer Code Manual for Vised Version 24E” (March, 2011). [Distributed on transmittal DVD in MCNP5\mcnp5_dist.tgz; will be extracted to MCNP5\utilities\VISUAL_EDITOR.]

Documentation on the MCNPDATA libraries may be found in Appendix G of the MCNPX manual and on the web http://www-xdiv.lanl.gov/projects/data/nuclear/mcnpdata.html

b)         background references:

D. B. Pelowitz, ed., MCNPX User's Manual, Version 2.6.0, Los Alamos National Laboratory report LA-CP-07-1473 (April 2008).

D. B. Pelowitz, ed., MCNPX User's Manual, Version 2.5.0, Los Alamos National Laboratory report LA-CP-05-0369 (April 2005).

L. S. Waters, ed., MCNPX User’s Manual, Version 2.4.0, Los Alamos National Laboratory report LA-CP-02-408 (Sept. 2002).

L. S. Waters, ed., MCNPX User’s Manual, Version 2.3.0, Los Alamos National Laboratory report LA-UR-02-2607 (April 2002).

J. F. Briesmeister, ed., MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, Los Alamos National Laboratory report LA-13709-M (April 2000).

R. E. Prael and H.Lichtenstein, User Guide to LCS: The LAHET Code System, Los Alamos National Laboratory report LA-UR-89-3014, Revised (September 15, 1989).

M. B. Chadwick, et al., “Cross Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX,” Nucl. Sci. Eng. 131 (3) 293 (March 1999).

M. B. Chadwick, et al., LA150 Documentation of Cross Sections, Heating, and Damage: Part A (Incident Neutrons) and Part B (Incident Protons), Los Alamos National Laboratory report LA-UR-99-1222 (1999).

S. G. Mashnik, A. J. Sierk, O. Bersillon, and T. A. Gabriel, “Cascade-Exciton Model Detailed Analysis of Proton Spallation at Energies from 10 MeV to 5 GeV,” Nucl. Instr. Meth. A414 (1998) 68. (Los Alamos National Laboratory Report LA-UR-97-2905).

G. Stepan, et al., CEM03.01 User Manual, Los Alamos National Laboratory report LA-UR-05-7321 (2005); RSICC Code Package PSR-532, http://www-rsicc.ornl.gov/codes/psr/psr5/psr-532.html/ (2006).

S. G. Mashnik, et al., CEM03.S1, CEM03.G1, LAQGSM03.S1, and LAQGSM03.G1 Versions of CEM03.01 and LAQGSM03.01 Event-Generators, Los Alamos National Laboratory report LA-UR-06-1764 (March 6, 2006), also available at http://mcnpx.lanl.gov > documents.

W. B. Wilson et al., “Recent Development of the CINDER'90 Transmutation Code and Data Library for Actinide Transmutation Studies," Proc. GLOBAL'95 Int. Conf. on Evaluation of Emerging Nuclear FuelCycle Systems, Versailles, France, p. 848, September 11-14, 1995.

11.        CONTENTS OF CODE PACKAGE

MCNPX is distributed on a single DVD in GNU compressed Unix tar files. WinZIP 8.0 is required to expand mcnpx files under Windows. The executable-only C00740MNYCP09 package includes MCNPX executables for PC Windows, PC Linux, and Sun/Solaris; MCNPDATA, test problems, and the referenced electronic documents listed in Section 10.a above.

The C00740MNYCP08 package.includes everything listed above, plus MCNPX Fortran and C source files, makefiles, and build scripts.

12.        DATE OF ABSTRACT

October 2008, revised February 2009, June 2011, July 2011.

KEYWORDS:       CHARGED PARTICLES; COMPLEX GEOMETRY; ELECTRON; GAMMA-RAY; HIGH ENERGY; KAON; MONTE CARLO; NEUTRON; PION; PROTON; RADIOGRAPHY; SPALLATION; RADIATION TRANSPORT


RSICC CODE PACKAGE CCC-740

Package NAME AND TITLE:

MCNP5/MCNPX:           Monte Carlo N–Particle Transport Code System Including MCNP5-1.60 and MCNPX 2.7.0 and Data Libraries.

 

This package contains MCNP5-1.60, MCNPX 2.7.0, and MCNPDATA. The code abstracts and the MCNPDATA information file are included in this same file.

 

The Readme information file for MCNPDATA follows:

 

Code name: MCNP / MCNPX / DATA

 

Version:     May 2008 Data Release for MCNP5 / MCNPX

         (RSICC first released these data in October 2008.)

 

LANL No.:    LA-CC-02-083, LA-CC-02-057

 

Files:       MCNP and MCNPX DATA:

100xs    531dos   532dos   actia      actib       dre5      drmccs

el       el03     endf5mt  endf5p     endf5u      endf60    endf62mt

endf66a  endf66b  endf66c  endf66d    endf66e     endf6dn   endf7u

endf70a  endf70b  endf70c  endf70d    endf70e     endf70f   endf70g 

endf70h  endf70i  endf70j  endf70k    endf70prot  endf70sab endl92

end192fp kidman   la150h   la150n     la150u      llldos    mcplib

mcplib02 mcplib03 mcplib04 mclib05t   mgxsnp      misc5xs   newxs  

newxsd   rmccs    rmccsa   sab2002    specs       t16_2003  therxs

tmccs    uresa    xsdir    xsdir05t   xsdir7u

 

Files:       MCNPX DATA Files:

atab.dat, barpol.dat, barpol2001.dat, bcdlib, bcdtp, channel1.tab,

cinder.dat, cindergl.dat, delay_library.dat, flalpha.tab, frldm.tab,

gamman.tbl, gdr.dat, level,tbl, mass.tbl, mollnix.tbl, pace2.data,

shell.tbl, and vgsld.tab

Date:        2008-05-09

 

Contacts:    Bob Little

Nuclear DATA Team Leader, XCP-Division, LANL

rcl@lanl.gov

 

MCNP DATA: Standard Neutron, Photoatomic, Photonuclear, and Electron Data

Libraries for MCNP and MCNPX.

 

These cross-section libraries are released by the Data Team in XCP-Division at Los Alamos National Laboratory for use with the MCNP/MCNPX Monte Carlo code packages. This release includes all of the XCP-Division distributed neutron and proton data libraries, the photoatomic libraries, photonuclear data library LA150U, the electron libraries EL1 and EL03, an updated XSDIR file, and a SPECS file for use with MAKXSF to convert the ascii data libraries into binary form. This release is intended to completely replace previous RSICC releases DLC-105, DLC-181, DLC-189, DLC-200, DLC-205 as well as the cross sections previously included with CCC-200/MCNP4A, CCC-710/MCNP5 1.30, and CCC-730/MCNP5 1.40/MCNPX 2.5.0. The release will be updated as new libraries become available.

 

This README file provides information regarding the data libraries contained in this release. The XSDIR file is specific to this release and may not work with previous packages. As of the November 2007 release (with MCNP5_RSICC_1.50), the default continuous energy neutron transport data with 389 isotopes and 3 elements are from the ENDF70 library (based upon the ENDF/B-VII.0 evaluations). The default proton transport data are from the ENDF70PROT library. Older data can be accessed by specifically requesting the identifier associated with each library.

 

The libraries MCPLIB04 and EL03 are the default libraries for photoatomic and electron transport respectively. ENDF70SAB is the default library for S(a,b), and LA150U is the default library for photonuclear transport. More information on the data libraries contained in this release is available in Appendix G of the MCNP5 manual or from the data team's web site at

     http://www-xdiv.lanl.gov/PROJECTS/DATA/nuclear/

 

Continuous-energy Neutron Data Libraries

The following lists the publicly released continuous-energy neutron data libraries for use with MCNP as of May 2008.

* endf70(a-k) - ENDF/B-VII Release 0

* t16_2003 - pre ENDF/B-VII.0 evaluations from Los Alamos Group T-16 for 15 isotopes

* actia and actib - ENDF/B-VI Release 8

* endf66(a-e) - ENDF/B-VI Release 6

* la150n: 150-MeV Neutron Library for MCNP

* uresa - ENDF/B-VI Release 4 with probability tables

* endf6dn - ENDF/B-VI Release 2 with delayed-neutron data

* endf62mt - multitemperature ENDF/B-VI Release 2

* endf60 - ENDF/B-VI Release 2

* newxs - LANL based evaluations

* rmccs - ENDF/B-V and LANL based evaluations

* rmccsa - ENDF/B-V and LANL based evaluations

* endf5p - ENDFB-V

* endf5u - ENDF/B-V

* misc5xs - Contains a number of previously released small libraries

* kidman - fission product evaluations

* 100xs - LANL based evaluations for a subset of isotopes up to 100 MeV

* endl92 - 1992 ENDL library from Lawrence Livermore National Lab (LLNL)

* end192pf

* endf5mt - Multitemperature data previously released as eprixs and u600k

 

Discrete Neutron Libraries

Discrete neutron cross sections are used with the DRXS input card in MCNP. The currently supported discrete neutron libraries are:

 

* newxsd - discrete version of newxs

* drmccs - discrete version of rmccs and rmccsa

* dre5 - discrete version of endf5u and endf5p

 

Photoatomic Data Libraries

There are now five photoatomic transport data libraries; mcplib, mcplib02, mcplib03, mcplib04, and mcplib05t.

 

MCNP Multigroup Data Libraries

The multigroup neutron and photon library mgxsnp is provided for use with MCNP, and is based primarily on ENDF/B-V evaluations

 

Photonuclear Data Libraries

We currently support two photonuclear libraries; la150u, endf7u.

 

Thermal Neutron Data Libraries

S(alpha,beta) data are contained in the tmccs, therxs, sab2002, and sab2007, endf70sab libraries. The endf70sab libraries are the default as of the May 2008 release.

 

Electron Data Libraries

el and el03 are the electron transport libraries.

 

Dosimetry Data Libraries

531dos, 532dos, and llldos are the publicly released dosimetry data libraries.

 

Proton Data Libraries

endf70prot and la150h are the proton transport libraries.

 

The data libraries, as distributed, are in ASCII, or type 1, format.

 

We refer you to the following web site for available documentation on each library:

http://www-xdiv.lanl.gov/projects/data/nuclear/mcnpdata.html

 

You may also e-mail questions to the MCNP forum at mcnp-forum@lanl.gov or to

nucldata@lanl.gov.