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CCC-0705 MCNPX 2.3.0.

MCNPX 2.3.0, Monte Carlo Code System for Multiparticle and High Energy Applications

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1. NAME OR DESIGNATION OF PROGRAM:  MCNPX 2.3.0
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
No item

Machines used:

No specified machine
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3. DESCRIPTION OF PROGRAM OR FUNCTION

MCNPX is a general-purpose Monte Carlo N-Particle code that extends the capabilities of the MCNP code. Among other new capabilities, MCNPX extends MCNP with support for additional particle types, new cross section libraries, and the ability to use physics models for energies where tabular data are not available.

Photonuclear capability in the tabular range is included in this release. Neutron tabular data are used as in MCNP4B; above the table energy limits, physics modules are used. Current physics modules include the Bertini and ISABEL models taken from the LAHET Code System (LCS) and CEM. An old version of FLUKA is available for calculations above the range of INC physics applicability.
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4. METHODS

MCNP treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and  second-degree surfaces and some special fourth-degree surfaces. Pointwise continuous-energy cross section data are used, although multigroup data may also be used. A general source and tally structure is available. The tallies have extensive statistical analysis of convergence. Rapid convergence is enabled by a wide variety of variance reduction methods.

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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Neutrons from 0.0 - 150.0 MeV in tabular range for 42 isotopes (except for 9Be to 100 MeV).

All materials involving neutron transport must use the same tabular upper energy limit.

Neutrons from 1.0 MeV in physics regime.

Protons from 1.0 to 150.0 MeV in tabular range for 41 isotopes.

Protons from 1.0 MeV in physics 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; delayed neutrons are treated as prompt.

Photoneutrons from 1.0 to 150.0 MeV in tabular range for 12 isotopes.

High energy portions of MCNPX version 2.3.0 above the tabular regime are not yet parallelized. Code contributors are available to assist those who wish to run in parallel in the tabular regime.
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6. TYPICAL RUNNING TIME

Runtime was 36 minutes for the test cases on a Pentium III 450Mhz running Linux, and 17 minutes on an IBM RS/6000 Model 270.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS


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. 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 DLC-205/MCNPXDATA or equivalent 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; minus the EL03 library because the EL03 library is incompatible with MCNP4B, upon which MCNPX 2.3.0 is based. 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 forcharged 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; however, some features specific to MCNP4C will not function. In particular, features related to probability tables and delayed neutrons will be ignored. Electron tables with zaid numbers ending in .01e will work, others will not.
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9. STATUS
No status
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10. REFERENCES

J. F. Briesmeister, ed.,
"MCNP-A General Monte Carlo N-Particle Transport Code," LA-12625-M, Version 4B (March 1997). The mcnp4b report is included in the DOC subdirectory on the distribution CD.

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 or Linux 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, and Intel Linux.. The compiled version of the code tends to run ~7 Mbytes. Dynamic allocation makes memory demands variable. Use of mesh and radiography tallies typically adds 1 word per bin.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS

C and Fortran 77 compilers and the GNU make utility are required for installation. The gnu77 compiler has a bug which causes test problem 14 to crash. This primarily affects Linux systems, and a fix is available from the contributors. Note that there is no Windows implementation for Version 2.3.0. Future releases will address the Windows operating system. 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.

- Redhat Linux Version 6.1 on 450 MHz Pentium III (9 nodes) with g77 and with pgf77.

- HP B1000 (PA-8500) under HP-UX 10.20 with Fortran 77 V0.20 and HP C V10.32.00 (compiled with no optimization).

- DEC 500 AU under Digital Unix 4.0D, DEC Fortran 5.1-8 and DEC C 5.6-075.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  There is no Windows implementation.
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Shielding Information Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Advanced Accelerator Applications
                Los Alamos National Laboratory,
                Los Alamos, New Mexico, U.S.A.
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16. MATERIAL AVAILABLE
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17. CATEGORIES

Keywords: Monte Carlo method, charged particles, coupled neutron gamma cross sections, electrons, geometry, neutron, protons, shielding, spallation.