RSICC CODE PACKAGE CCC-710/MCNP5

1. NAME AND TITLE

MCNP5: Monte Carlo N-Particle Transport Code System.

AUXILIARY PROGRAMS

MAKXSF:  Prepares MCNP Cross-Section Libraries.

VISED: Visual Editor for interactively constructing & visualizing MCNP geometry
             (for Windows PCs only)
 

RELATED DATA LIBRARY

MCNP5DATA:  Standard Neutron, Photoatomic, Photonuclear, and Electron Data Libraries for MCNP5.

The following data libraries for MCNP5 are included in this package: Documentation on the data libraries may be found in Appendix G of the MCNP5 manual (Volume I)
A separate test library of cross sections is used for running the sample problems, but the test library is not suitable for real problems.
 

2. CONTRIBUTOR

Diagnostics Applications Group, Los Alamos National Laboratory, Los Alamos, New Mexico.

3. CODING LANGUAGE AND COMPUTERS

Fortran 90 and C; Unix systems, Windows PCs, Linux systems, Macintosh with MacOSX, Itanium.
 

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.

New features in MCNP5 which were not available in the previous MCNP4C2 version are:

* Doppler broadening for photon cross-sections
* Radiography tallies
* Generalized source options
* Time-dependent importances
* Extended period random number generator
* Superimposed mesh-based tallies
* Additional Macrobodies
* Edits of important criticality safety parameters
* Plotting enhancements
* Improved build system for compiling and testing
* Improved support for parallel operation using MPI and OpenMP
See the MCNP home page more information http://mcnp.lanl.gov with a link to the MCNP Forum. See the Electronic Notebook at http://www-rsicc.ornl.gov/rsic.html for information on user experiences with MCNP.
 

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(alpha,beta) models. For photons, the code accounts for incoherent and coherent scattering, the possibility of fluorescent emission after photoelectric absorption, absorption in pair production with local emission of annihilation radiation, and bremsstrahlung. A continuous-slowing-down model is used for electron transport that includes positrons, k x-rays, and bremsstrahlung, but does not include external or self-induced fields. 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. The tallies have extensive statistical analysis of convergence. Rapid convergence is enabled by a wide variety of variance reduction methods. Energy ranges are 0-20 MeV for neutrons (with data available up to 150 MeV for many nuclides), 1 keV - 1 GeV for electrons, and 1 keV - 100 GeV for photons.
 

6. RESTRICTIONS OR LIMITATIONS

None noted.
 

7. TYPICAL RUNNING TIME

On a 1 GHz Pentium-III, compilation of MCNP5 takes about 5 minutes, and the 42 test cases run in about 4 minutes.
 

8. COMPUTER HARDWARE REQUIREMENTS

MCNP is operable on workstations or PC's running Unix or Linux, Windows-based PC's, Macintosh computers with MacOSX, and Itanium computers. Executable files for Windows- and Linux-based PC's are provided. Expanding the code system requires 70 MB, and expanding the ASCII cross sections require 2.3 GB of hard disk space.
 

9. COMPUTER SOFTWARE REQUIREMENTS

Executables are included for Windows and Linux users, so users who want to run these executables do not require a compiler. Other computer users must have compilers. Compilation of MCNP5 requires both Fortran-90 and ANSI C standard compilers.

  computer/OS                 Fortran-90

 SGI IRIX64                   MIPSpro 7.3.0 & higher
 HP/Compaq Alpha OSF1         Fortran 5.3-915 & higher
 IBM AIX 4.3 & higher         xlf90 7.1
 Sun SunOS                    f90 6.1 & higher

 PC Linux                     Absoft Pro 8.0
                              Lahey Pro 6.1e
                              PGF90 4.0 (not 4.1 - has bugs)
                              Intel 7.1

 PC Windows                   HP/Compaq CVF 6.6a & higher
 (95,98,ME,XP,2000)           Absoft Pro 8.0
                              Lahey Pro 6.1e

 Apple G4 MacOSX              Absoft Pro 8.0
    (10.2.4)
 Itanium Linux                Intel 7.1

Threaded parallelism with OpenMP has been tested on the SGI, Alpha, and IBM systems, both with and without MPI. MPI or PVM based parallelism has been tested on the SGI, Alpha, IBM, PC/Linux, and PC/Windows systems, using the vendor-supplied MPI,  MPICH (on Linux and Windows), or PVM 3.4.3. It should be noted that while we still support PVM, we highly recommend using MPI instead. Applications on the LANL parallel computers use MPI, and that is the basis for nearly all of our parallel development & testing for MCNP5; PVM is tested only sporadically.

Concerning Apple systems, we have only compiled and tested MCNP5 on G4 systems using Mac OSX 10.2.4 or higher. We will probably not support older Mac systems.

For compiling MCNP5 on Windows PCs, the Cygwin environment must first be installed. The Cygwin environment is a collection of GNU-based Unix utilities which have been ported to the Windows environment. 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 XFree86.

RSICC tested this release on the following systems:


 
 
 

10. REFERENCES

The Adobe Acrobat Reader freeware is available from http://www.adobe.com to read and print the electronic documentation.

a. Included documentation in electronic format on the CD:

  • README.txt
  • install_readme.txt
  • MCNP5_Install_Guide.pdf, "Installing and Running MCNP on Various Systems," Appendix C of LA-CP-03-0284.
  • b. Included in electronic format; will be expanded to the MCNP5/Manual subdirectory:
  • X-5 Monte Carlo Team, "MCNP — A General Monte Carlo N-Particle Transport Code, Version 5 - Volume I: Overview and Theory," LA-UR-03-1987  [file MCNP5_manual_VOL_I.pdf]  (May, 2003).
  • X-5 Monte Carlo Team, "MCNP — A General Monte Carlo N-Particle Transport Code, Version 5 - Volume II: Users Guide," LA-CP-03-0245 [file MCNP5_manual_VOL_II.pdf]  (May, 2003).
  • X-5 Monte Carlo Team, "MCNP — A General Monte Carlo N-Particle Transport Code, Version 5 - Volume III: Developers Guide," LA-CP-03-0284 [file MCNP5_manual_VOL_III.pdf]  (May, 2003).
  • J.T. Goorley, F.B. Brown, L. J. Cox,  "MCNP5 Improvements for Windows PCs," LA-UR-02-7162 [file MCNP5PCs.pdf]  (April, 2003).
  • L.L. Carter and R.A. Schwarz, "MCNP Visual Editor Computer Code Manual," [file VISED_manual.pdf]  (2002).
  • C. D. Harmon, II, R. D. Busch, J. F. Briesmeister, R. A. Forster, "Criticality Calculations with MCNP: A Primer," LA-12827-M  [file CriticalityPrimer.pdf]  (August 1994).
  • c. Included in electronic format; will be expanded to the MCNPDATA subdirectory:
  • readme_data.txt
  • X-5 Data Team, "CCC-710/MCNP: Data Libraries for MCNP," [file CCC-710_DATA.pdf]  (May, 2003).

  • 11. CONTENTS OF CODE PACKAGE

    Included are the referenced electronic documents in (10.a-c) and the source codes, test problems, Linux and PC executables, and installation scripts transmitted on CD in Windows and UNIX format. The ASCII MCNP5DATA data library is included on the distribution media. See the README files for details on package contents and installation.
     

    12. DATE OF ABSTRACT

    May 2003.
     

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