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MCNP5


  • X-5 Monte Carlo Team, “MCNP – A General N-Particle Transport Code, Version 5
    • Volume I: Overview and Theory”, LA-UR-03-1987 (April, 2003).
    • Volume II: User’s Guide”, LA-CP-03-0245 (April, 2003).
    • Volume III: Developer’s Guide”, LA-CP-03-0284 (April, 2003).
  • MCNP5-1.60 Release
    • Forrest Brown, Brian Kiedrowski, Jeffrey Bull, "MCNP5-1.60 Release Notes", LA-UR-10-06235 (2010).
    • Brian Kiedrowski, Forrest Brown, Jeffrey Bull, et al., "MCNP5-1.60 Feature Enhancements and Manual Clarifications", LA-UR-10-06217 (2010).
    • Forrest Brown, Brian Kiedrowski, Jeffrey Bull, Matthew Gonzales, Nathan Gibson, "Verification of MCNP5-1.60", LA-UR-10-05611 (2010).
  • Additional Verification-Validation

Availability: MCNP is distributed within the United States by the Radiation Safety Information Computational Center (RSICC) --- formerly, Radiation Shielding Information Center (RSIC), Oak Ridge, Tennessee. There are versions for virtually all systems asked about (PC, Sun Solaris, etc.). Please contact RSICC directly.

MCNP has been distributed internationally by the Nuclear Energy Agency (OECD/NEA), Paris, France. The distribution is the same package as that from RSICC. Please contact the OECD/NEA Computer Program Service.

 

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