CCC-0715 MCNPX 2.4.0.
MCNPX 2.4.0, Monte Carlo N-Particle Transport Code System for Multiparticle and High Energy Applications.
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, FEATURES, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, SOFTWARE REQUIREMENTS, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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3. DESCRIPTION OF PROGRAM OR FUNCTION
MCNPX is a general purpose Monte Carlo radiation transport code that tracks all element particles up to GeV range energies. Version MCNPX 2.4.0 combines MCNP4C3, a general purpose, continuous energy, generalised geometry, time dependent, coupled neutron-photon-electron Monte Carlo transport codesystem for energies up to 20 MeV and MCNPX 2.3.0 the previous version of MCNPX, LAHET 2.8 a code system for high energy particle transport calculations (in particular nucleons and pions in the medium energy range) and CEM a cascade exciton model for nuclear reactions by the Monte-Carlo method.
Current applications for the code include among others:
- Design of accelerator spallation targets, particularly for neutron scattering facilities.
- Investigations for accelerator isotope production and destruction programs, including the transmutation of nuclear waste.
- Research into accelerator-driven energy sources.
- Medical physics, especially proton and neutron therapy.
- Investigations of cosmic-ray radiation backgrounds and shielding for high altitude aircraft and spacecraft.
- Accelerator-based imaging technology such as neutron and proton radiography.
- Design of shielding in accelerator facilities.
- Activation of accelerator components and surrounding groundwater and air.
- Investigation of fully coupled neutron-charged particle transport for lower-energy applications.
- High-energy dosimetry and neutron detection.
- Charged-particle tracking in plasmas.
- Charged-particle propulsion concepts for spaceflight.
- Single-event upset in semiconductors, from cosmic rays in spacecraft or from the neutron component on the earth's surface.
- Detection technology using charged particles
- Nuclear Safeguards
- Radiation protection and shielding
- etc.
MCNPX is a general purpose Monte Carlo radiation transport code that tracks all element particles up to GeV range energies. Version MCNPX 2.4.0 combines MCNP4C3, a general purpose, continuous energy, generalised geometry, time dependent, coupled neutron-photon-electron Monte Carlo transport codesystem for energies up to 20 MeV and MCNPX 2.3.0 the previous version of MCNPX, LAHET 2.8 a code system for high energy particle transport calculations (in particular nucleons and pions in the medium energy range) and CEM a cascade exciton model for nuclear reactions by the Monte-Carlo method.
Current applications for the code include among others:
- Design of accelerator spallation targets, particularly for neutron scattering facilities.
- Investigations for accelerator isotope production and destruction programs, including the transmutation of nuclear waste.
- Research into accelerator-driven energy sources.
- Medical physics, especially proton and neutron therapy.
- Investigations of cosmic-ray radiation backgrounds and shielding for high altitude aircraft and spacecraft.
- Accelerator-based imaging technology such as neutron and proton radiography.
- Design of shielding in accelerator facilities.
- Activation of accelerator components and surrounding groundwater and air.
- Investigation of fully coupled neutron-charged particle transport for lower-energy applications.
- High-energy dosimetry and neutron detection.
- Charged-particle tracking in plasmas.
- Charged-particle propulsion concepts for spaceflight.
- Single-event upset in semiconductors, from cosmic rays in spacecraft or from the neutron component on the earth's surface.
- Detection technology using charged particles
- Nuclear Safeguards
- Radiation protection and shielding
- etc.
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4. METHODS
The Monte Carlo method is used and an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and some special fourth-degree surfaces can be treated.
For the lower energy region of neutrons and photons pointwise continuous-energy cross section data are used,
It contains intermediate interaction physics includes models for
- Intranuclear Cascade Models
- Multistage Pre-equilibrium Models (MPM)
- Fermi-Breakup Model
- Evaporation Model
- Level Densities
- High-Energy Fission
- High-Energy Interactions
contains an early version of the FLUKA high-energy code.
As to Nuclear Data Tables the following approach is used:
For low energy neutrons, tabular data is used from continous energy libraries as for MCNP.
A variety of Variance Reduction Techniques and Improved Tallies and Data Analysis is included
The Monte Carlo method is used and an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and some special fourth-degree surfaces can be treated.
For the lower energy region of neutrons and photons pointwise continuous-energy cross section data are used,
It contains intermediate interaction physics includes models for
- Intranuclear Cascade Models
- Multistage Pre-equilibrium Models (MPM)
- Fermi-Breakup Model
- Evaporation Model
- Level Densities
- High-Energy Fission
- High-Energy Interactions
contains an early version of the FLUKA high-energy code.
As to Nuclear Data Tables the following approach is used:
For low energy neutrons, tabular data is used from continous energy libraries as for MCNP.
A variety of Variance Reduction Techniques and Improved Tallies and Data Analysis is included
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
All standard MCNP neutron libraries over their stated ranges.
Neutrons in the LA150 library from 0.0 - 150.0 MeV in tabular range for 42 isotopes (except for 9Be to 100 MeV).
Neutrons from 1.0 MeV in physics model regime.
Protons from 1.0 to 150.0 MeV in tabular range for 41 isotopes.
Protons from 1.0 MeV in physics model regime.
Pions, muons, and kaons are treated only by physics models.
Photons from 1 keV - 100 GeV.
Electrons from 1 keV - 1 GeV.
Neutrons do not create delayed photons.
Photonuclear interactions from 1.0 to 150.0 MeV in tabular range for 12 isotopes. No physics models outside the tabular range are available in MCNPX 2.4.0.
For any incident particle where libraries exist (neutrons, protons, and photonuclear), MCNPX 2.4.0 users should not specify isotopes with different transition energies between tabular data and physics models. The transition energies should be the same for each incident particle and should not exceed the maximum energy of the selected data library.
All standard MCNP neutron libraries over their stated ranges.
Neutrons in the LA150 library from 0.0 - 150.0 MeV in tabular range for 42 isotopes (except for 9Be to 100 MeV).
Neutrons from 1.0 MeV in physics model regime.
Protons from 1.0 to 150.0 MeV in tabular range for 41 isotopes.
Protons from 1.0 MeV in physics model regime.
Pions, muons, and kaons are treated only by physics models.
Photons from 1 keV - 100 GeV.
Electrons from 1 keV - 1 GeV.
Neutrons do not create delayed photons.
Photonuclear interactions from 1.0 to 150.0 MeV in tabular range for 12 isotopes. No physics models outside the tabular range are available in MCNPX 2.4.0.
For any incident particle where libraries exist (neutrons, protons, and photonuclear), MCNPX 2.4.0 users should not specify isotopes with different transition energies between tabular data and physics models. The transition energies should be the same for each incident particle and should not exceed the maximum energy of the selected data library.
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8. RELATED OR AUXILIARY PROGRAMS
AUXILIARY PROGRAMS:
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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
RELATED DATA LIBRARIES:
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Libraries specific to the LAHET Bertini model are included in a file called BERTIN. Gamma production cross sections from spallation products are included in a file called PHTLIB. A new version of PHTLIB is available for MCNPX 2.4.0, including improved data and also metastable state information. High-energy total, reaction and elastic cross sections are contained in a file called BARPOL.DAT.
MCNPX includes a test library of cross sections for running the sample problems, but the test library is not suitable for real problems. Running the code requires continuous energy cross section data included in the ZZ-MCNPXDATA 2.4.0 package or equivalent data.
The ZZ-MCNPXDATA 2.4.0 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. 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 MCNP4B (originally distributed in DLC-189 and now included in DLC-205) can be used with MCNPX; however, they will not contain emission data for charged particles or recoil nuclei; therefore, theseproducts will not be produced and tracked. All neutron, photon and electron libraries developed for use with MCNP4C will work with MCNPX2.4.0.
AUXILIARY PROGRAMS:
------------------
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
RELATED DATA LIBRARIES:
----------------------
Libraries specific to the LAHET Bertini model are included in a file called BERTIN. Gamma production cross sections from spallation products are included in a file called PHTLIB. A new version of PHTLIB is available for MCNPX 2.4.0, including improved data and also metastable state information. High-energy total, reaction and elastic cross sections are contained in a file called BARPOL.DAT.
MCNPX includes a test library of cross sections for running the sample problems, but the test library is not suitable for real problems. Running the code requires continuous energy cross section data included in the ZZ-MCNPXDATA 2.4.0 package or equivalent data.
The ZZ-MCNPXDATA 2.4.0 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. 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 MCNP4B (originally distributed in DLC-189 and now included in DLC-205) can be used with MCNPX; however, they will not contain emission data for charged particles or recoil nuclei; therefore, theseproducts will not be produced and tracked. All neutron, photon and electron libraries developed for use with MCNP4C will work with MCNPX2.4.0.
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10. REFERENCES
J. F. Briesmeister, Ed., "MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M (April 2000).
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.
M. B. Chadwick, P. G. Young, R. E. MacFarlane, P. Moller, G. M. Hale, R. C. Little, A. J. Koning and S. Chiba, "LA150 Documentation of Cross Sections, Heating, and Damage: Part A (Incident Neutrons) and Part B (Incident Protons)," LA-UR-99-1222 (1999).
H. G. Hughes, et. al., "MCNPX for Neutron-Proton Transport," International Conference on Mathematics & Computation, Reactor Physics & Environmental. Analysis in Nuclear Applications, American Nuclear Society, Madrid, Spain (September 27-30, 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).
R. E. Prael and H.Lichtenstein, "User Guide to LCS: The LAHET Code System," LA-UR-89-3014, Revised (September 15, 1989).
J. F. Briesmeister, Ed., "MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M (April 2000).
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.
M. B. Chadwick, P. G. Young, R. E. MacFarlane, P. Moller, G. M. Hale, R. C. Little, A. J. Koning and S. Chiba, "LA150 Documentation of Cross Sections, Heating, and Damage: Part A (Incident Neutrons) and Part B (Incident Protons)," LA-UR-99-1222 (1999).
H. G. Hughes, et. al., "MCNPX for Neutron-Proton Transport," International Conference on Mathematics & Computation, Reactor Physics & Environmental. Analysis in Nuclear Applications, American Nuclear Society, Madrid, Spain (September 27-30, 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).
R. E. Prael and H.Lichtenstein, "User Guide to LCS: The LAHET Code System," LA-UR-89-3014, Revised (September 15, 1989).
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11. HARDWARE REQUIREMENTS
MCNPX runs under Unix, Linux, and Windows operating systems and has been implemented on IBM RS/6000 AIX, DEC Alpha Digital Unix, SGI IRIX 32 and 64-bit, HP HP-UX version 10, Sun Solaris, Intel Linux, and Windows-based PC's. The compiled version of the code tends to run ~8 Mbytes. Dynamic allocation makes memory demands variable on all platforms.
MCNPX runs under Unix, Linux, and Windows operating systems and has been implemented on IBM RS/6000 AIX, DEC Alpha Digital Unix, SGI IRIX 32 and 64-bit, HP HP-UX version 10, Sun Solaris, Intel Linux, and Windows-based PC's. The compiled version of the code tends to run ~8 Mbytes. Dynamic allocation makes memory demands variable on all platforms.
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13. 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/Downloads_terms.htm. This is a Fortran 90 version of MCNPX which uses standard F90 allocation schemes for dynamic variables on all platforms. RSICC tested this release on the following systems:
AIX 4.3.3 (IBM 43P-260) with XL C/C++ 4.4; XL Fortran 6.1.
Dell PowerEdge6400 running RedHat Linux 7.0 with PGF90 4.0-2 and gcc.
Intel Pentium running RedHat Linux 6.1 with PGF90 3.3-2 and pgcc.
Sun UltraSparc 60 under SunOS5.6 with F90 2.0 and C++ 5.0.
The LANL developers ran MCNPX 2.4.0 on the following systems. Their executables are included in the distribution. Installation may fail with different compilers.
Sun-Solaris/WorkShop Fortran Compilers 6, update 2 (Fortran 95 6.2)
SGI-IRIX/MIPSpro Compilers: Version 7.30 under 64 bit IRIX and 32 bit IRIX
HP-HPUX/HP F90 v2.4.10
IBM-AIX/xlf90 Version 7 Release 1
DEC Alpha-Tru64 running OSF1 V5.0 with Compaq Fortran V5.3-915
Intel-Linux 7 with The Portland Group Fortran Group, Inc. f90 3.2-3
Windows2000 on Pentium IV - Compaq Visual Studio 6.6 and Microsoft C++ 6.0
(Note that Compaq Visual Studio 6.5 fails to compile the code, but 6.1 works.)
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/Downloads_terms.htm. This is a Fortran 90 version of MCNPX which uses standard F90 allocation schemes for dynamic variables on all platforms. RSICC tested this release on the following systems:
AIX 4.3.3 (IBM 43P-260) with XL C/C++ 4.4; XL Fortran 6.1.
Dell PowerEdge6400 running RedHat Linux 7.0 with PGF90 4.0-2 and gcc.
Intel Pentium running RedHat Linux 6.1 with PGF90 3.3-2 and pgcc.
Sun UltraSparc 60 under SunOS5.6 with F90 2.0 and C++ 5.0.
The LANL developers ran MCNPX 2.4.0 on the following systems. Their executables are included in the distribution. Installation may fail with different compilers.
Sun-Solaris/WorkShop Fortran Compilers 6, update 2 (Fortran 95 6.2)
SGI-IRIX/MIPSpro Compilers: Version 7.30 under 64 bit IRIX and 32 bit IRIX
HP-HPUX/HP F90 v2.4.10
IBM-AIX/xlf90 Version 7 Release 1
DEC Alpha-Tru64 running OSF1 V5.0 with Compaq Fortran V5.3-915
Intel-Linux 7 with The Portland Group Fortran Group, Inc. f90 3.2-3
Windows2000 on Pentium IV - Compaq Visual Studio 6.6 and Microsoft C++ 6.0
(Note that Compaq Visual Studio 6.5 fails to compile the code, but 6.1 works.)
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Keywords: Monte Carlo method, charged particles, electrons, gamma ray, high energy, neutron, protons, spallation.