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Monte Carlo N-Particle Transport Code

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MCNP
Developer(s)LANL
Stable release
MCNPX 2.7.E (Beta) / March 3, 2011; 14 years ago (2011-03-03)[1]
Written inFortran 90
Operating systemCross-platform
TypeComputational physics
LicenseMCNPX Single-User Software License (proprietary)
Websitehttp://mcnpx.lanl.gov/

Monte Carlo N-Particle Transport Code (MCNP) is a software package for simulating nuclear processes. It is developed by Los Alamos National Laboratory since at least 1957[2] with several further major improvements. It is distributed within the United States by the Radiation Safety Information Computational Center in Oak Ridge, TN and internationally by the Nuclear Energy Agency in Paris, France. It is used primarily for the simulation of nuclear processes, such as fission, but has the capability to simulate particle interactions involving neutrons, photons, and electrons. "Specific areas of application include, but are not limited to, radiation protection and dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, detector design and analysis, nuclear oil well logging, accelerator target design, fission and fusion reactor design, decontamination and decommissioning."

MCNPX (Monte Carlo N-Particle eXtended) was also developed at Los Alamos National Laboratory, and is capable of simulating particle interactions of 34 different types of particles (nucleons and ions) and 2000+ heavy ions at nearly all energies,[3] including those simulated by MCNP.

Both codes can be used to judge whether or not nuclear systems are critical and to determine doses from sources, among other things.

Notes

  1. ^ "MCNPX home Page". LANL. 4 March 2011. Archived from the original on 21. July 2011. Retrieved 7 December 2012. {{cite web}}: Check date values in: |archivedate= (help)
  2. ^ Cashwell, E.D.; Everett, C.J. (1959). A Practical Manual on the Monte Carlo Method for Random Walk Problems (PDF). London: Pergamon Press.
  3. ^ https://mcnpx.lanl.gov/opendocs/misc/FeaturesList.pdf

See also

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