MCNP® and Monte Carlo N-Particle® are registered trademarks owned by Los Alamos National Security, LLC, manager and operator of Los Alamos National Laboratory. Any third party use of such registered marks should be properly attributed to Los Alamos National Security, LLC, including the use of the ® designation as appropriate. Please note that trademarks are adjectives and should not be pluralized or used as a noun or a verb in any context for any reason. Any questions regarding licensing, proper use, and/or proper attribution of Los Alamos National Security, LLC marks should be directed to trademarks@lanl.gov.
MCNP6.1/MCNP5/MCNPX: Monte Carlo N–Particle Transport Code System Including MCNP6.1, MCNP5-1.60, MCNPX-2.7.0 and Data Libraries.
Note: No changes have been made to the MCNP5 and MCNPX codes included in this package.
1. MCNP6.1: Monte Carlo N–Particle Transport Code System, MCNP6.1.
RELATED DATA LIBRARIES
MCNPDATA: ENDF/B-VII.1 nuclear and atomic data.
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.
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.
Los Alamos National Laboratory, Los Alamos, New Mexico.
Package ID: C00810MNYCP00:
Fortran 90 and C source code and executables for Windows PCs, Linux PCs, and MacOSX.
Package ID: C00810MNYCP01:
Executables only (no source code) for Windows PCs, Linux PCs, Macintosh with MacOSX.
MCNP6® is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. MCNP6 represents the culmination of a multi-year effort to merge the MCNP5® [X-503] and MCNPX® [PEL11] codes into a single product comprising all features of both. For those familiar with previous versions of MCNP, you will discover the code has been expanded to handle a multitude of particles and to include model physics options for energies above the cross-section table range, a material burnup feature, and delayed particle production. Expanded and/or new tally, source, and variance-reduction options are available to the user as well as an improved plotting capability. The capability to calculate keff eigenvalues for fissile systems remains a standard feature. Although MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, the result is much more than the sum of these two computer codes. MCNP6 is the result of five years of effort by the MCNP5 and MCNPX code development teams. These groups of people, residing in the Los Alamos National Laboratory's (LANL) X Computational Physics Division, Monte Carlo Codes Group (XCP-3), and Nuclear Engineering and Nonproliferation Division, Systems Design and Analysis Group (NEN-5, formerly D-5), have combined their code development efforts to produce the next evolution of MCNP. While maintenance and bug fixes will continue for MCNP5 v.1.60 and MCNPX v.2.7.0 for upcoming years, new code development capabilities will be developed and released only in MCNP6. In fact, this initial production release of MCNP6 (v. 1.0) contains 16 new features not previously found in either code. These new features include (among others) the abilities to import unstructured mesh geometries from the finite element code Abaqus, to transport photons down to 1.0 eV, to model complete atomic relaxation emissions, and to generate or read mesh geometries for use with the LANL discrete ordinates code PARTISN.
In addition to the code capabilities of MCNP5 and MCNPX, MCNP6 includes several significant new capabilities not found in either of the parent codes. These capabilities are described below.
Adjoint-based sensitivity coefficients
Geometry mesh file creation
Unstructured mesh geometry
Low energy photon and electron transport for atomic cross sections
Complete photon-induced atomic relaxation
Explicit tracking of all charged particles in magnetic fields
Nested dxtran spheres
Uncollided secondaries
Time bins for mesh tallies
Enhanced photon form factors
Surface and cell flagging are now possible with MCNP5-style mesh tallies
Upgrade to CEM03.03 and LAQGSM03.03
Generation of gamma rays from muonic atoms
Pre-collision next event estimator
Double differential particle interaction cross section generator
New MCNP6 Depletion Capabilities
Cosmic Ray sources (SDEF card, PAR keyword)
Support High-Fidelity Skymap Data Files
64-Bit Windows Plotting support
Background source option (SDEF card, PAR option)
Pulse Height trigger tally option (FT card, PHL option)
Built-in photon detector response curves (FT card, PHL option)
Capture trigger tally option (FT card, CAP keyword)
First-fission tally option (FT card, FFT keyword)
Delayed Beta treatment (ACT card)
Spontaneous beta source option (SDEF card, PAR keyword)
Delayed-particles from photonuclear library interactions
New data path directories & default xsdir names
New installers
Data library (only) driven transport for n,p,e by default
Continuous thermal scattering laws S(α,β)
Perturbations for keff
Updates to Delayed Particle Model Package
MCNP6 will not exactly recreate the particle tracks of either MCNP5 nor MCNPX because several default options have been changed. Users should be aware that this first production release does contain several limitations. Although individual MCNP5 and MCNPX features work, full interoperability between MCNP5, X and 6 features does not necessarily exist, and this large combination of features has not been extensively tested. While there has been a significant amount of V&V behind MCNP6 already, and this V&V is made available with the MCNP6 distribution, users have been cautioned and continue to be cautioned that they are responsible for V&V for their own particular application of the code. It is expected that users of this initial release apply MCNP6 to the problems that they know well and have some intuition about, and report back to the MCNP6 team (email mcnp6@lanl.gov) their findings, either pro or con. Evidence for appropriate performance of MCNP6 should be added to the MCNP6 documentation and verification test suites, and evidence of discrepancies, especially discrepancies with MCNP5 1.60 or MCNPX 2.7.0, should be submitted for investigation.
Problem dependent.
MCNP6 will operate on most systems.
MCNP6 runs on PC's under Windows (Cygwin), Linux, and MacOSX. The code has improved support for newer Fortran 90 compilers. Included executables were created with the following compilers:
Linux: Intel 12.0.8 Plotting and OMP
Windows 7: Intel 11.1 Plotting and OMP
MacOS 10.7.5: Intel 12.1.1 Plotting and OMP.
Included documentation in electronic format to be extracted to your hard drive:
Initial MCNP6 Release Overview MCNP6 Version 1.0, Los Alamos National Laboratory report LA-UR-13-22934.
Many more reference documents (~650 total) on MCNP are included in the MCNP REFS
directory of this distribution.
The MCNP6.1/MCNP5/MCNPX package is distributed on 3 DVDs that can be read on Windows, Linux or MacOS. Disc 1 of C00810MNYCP00 contains MCNP6.1, MCNP5, MCNPX source code, pre-compiled executables and approximately 650 reference documents. Disc 1 of C00810MNYCP01 contains only the pre-compiled executables and the reference documents. Disks 2 and 3 of both packages contain the same ENDF/B-VII.1 data.
12. DATE OF ABSTRACT
August 2013.
KEYWORDS: COMPLEX GEOMETRY; COUPLED; CROSS SECTIONS; ELECTRON; GAMMA-RAY; MONTE CARLO; NEUTRON
*************************
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.
Los Alamos National Laboratory, Los Alamos, New Mexico.
Package ID: C00810MNYCP00:
Fortran 90 and C source code and executables for Windows PCs, Linux PCs, and MacOSX.
Package ID: C00810MNYCP01:
Executables only (no source code) for Windows PCs, Linux PCs, Macintosh with MacOSX.
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.
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.
Energy ranges are noted above.
On a 2 GHz Pentium 4, compilation of MCNP5 takes about 3 minutes, and the 50 regression test cases run in about 2 minutes.
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.
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 C00740MNYCP06 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).
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.
The MCNP6.1/MCNP5/MCNPX package is distributed on 3 DVDs that can be read on Windows, Linux or MacOS. Disc 1 of C00810MNYCP00 contains MCNP6.1, MCNP5, MCNPX source code, pre-compiled executables and approximately 650 reference documents. Disc 1 of C00810MNYCP01 contains only the pre-compiled executables and the reference documents. Disks 2 and 3 of both packages contain the same ENDF/B-VII.1 data.
October 2008, revised February 2009, September 2010; June 2011; August 2013.
KEYWORDS: COMPLEX GEOMETRY; COUPLED; CROSS SECTIONS; ELECTRON; GAMMA-RAY; MONTE CARLO; NEUTRON
*************************
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).
Los Alamos National Laboratory, Los Alamos, New Mexico.
Fortran 90 and C and exes; Windows & Linux PCs, Sun; IBM; DEC (C00810MNYCP00).
Executables (no source code) for Windows PCs, Linux PCs (C00810MNYCP01).
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.
MCNPX® 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/.
All capabilities of MCNP4C3 have been retained. Consult the MCNPX User’s Manual for applicability to high energy applications.
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.
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.
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.
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.
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.
The MCNP6.1/MCNP5/MCNPX package is distributed on 3 DVDs that can be read on Windows, Linux or MacOS. Disc 1 of C00810MNYCP00 contains MCNP6.1, MCNP5, MCNPX source code, pre-compiled executables and approximately 650 reference documents. Disc 1 of C00810MNYCP01 contains only the pre-compiled executables and the reference documents. Disks 2 and 3 of both packages contain the same ENDF/B-VII.1 data.
October 2008, revised February 2009, June 2011, August 2013.
KEYWORDS: CHARGED PARTICLES; COMPLEX GEOMETRY; ELECTRON; GAMMA-RAY; HIGH ENERGY; KAON; MONTE CARLO; NEUTRON; PION; PROTON; RADIOGRAPHY; SPALLATION; RADIATION TRANSPORT
MCNP® and Monte Carlo N-Particle® are registered trademarks owned by Los Alamos National Security, LLC, manager and operator of Los Alamos National Laboratory. Any third party use of such registered marks should be properly attributed to Los Alamos National Security, LLC, including the use of the ® designation as appropriate. Please note that trademarks are adjectives and should not be pluralized or used as a noun or a verb in any context for any reason. Any questions regarding licensing, proper use, and/or proper attribution of Los Alamos National Security, LLC marks should be directed to trademarks@lanl.gov.