THE MCNPX MONTE CARLO RADIATION TRANSPORT CODE
Abstract
MCNPX (Monte Carlo NParticle eXtended) is a generalpurpose Monte Carlo radiation transport code with threedimensional geometry and continuousenergy transport of 34 particles and light ions. It contains flexible source and tally options, interactive graphics, and support for both sequential and multiprocessing computer platforms. MCNPX is based on MCNP4B, and has been upgraded to most MCNP5 capabilities. MCNP is a highly stable code tracking neutrons, photons and electrons, and using evaluated nuclear data libraries for lowenergy interaction probabilities. MCNPX has extended this base to a comprehensive set of particles and light ions, with heavy ion transport in development. Models have been included to calculate interaction probabilities when libraries are not available. Recent additions focus on the time evolution of residual nuclei decay, allowing calculation of transmutation and delayed particle emission. MCNPX is now a code of great dynamic range, and the excellent neutronics capabilities allow new opportunities to simulate devices of interest to experimental particle physics; particularly calorimetry. This paper describes the capabilities of the current MCNPX version 2.6.C, and also discusses ongoing code development.
 Authors:
 Los Alamos National Laboratory
 Publication Date:
 Research Org.:
 Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
 OSTI Identifier:
 1000501
 Report Number(s):
 LAUR070150
TRN: US1100138
 DOE Contract Number:
 AC5206NA25396
 Resource Type:
 Conference
 Resource Relation:
 Conference: HADRONIC SHOWER SIMULATION WORKSHOP (HSSO6) ; 200609 ; BATAVIA
 Country of Publication:
 United States
 Language:
 English
 Subject:
 99; A CODES; CALORIMETRY; COMPUTERS; DECAY; ELECTRONS; GEOMETRY; HEAVY IONS; INTERACTIVE DISPLAY DEVICES; LIGHT IONS; NEUTRONS; NUCLEI; PHOTONS; PHYSICS; RADIATION TRANSPORT; SIMULATION; TRANSMUTATION; TRANSPORT
Citation Formats
WATERS, LAURIE S., MCKINNEY, GREGG W., DURKEE, JOE W., FENSIN, MICHAEL L., JAMES, MICHAEL R., JOHNS, RUSSELL C., and PELOWITZ, DENISE B. THE MCNPX MONTE CARLO RADIATION TRANSPORT CODE. United States: N. p., 2007.
Web.
WATERS, LAURIE S., MCKINNEY, GREGG W., DURKEE, JOE W., FENSIN, MICHAEL L., JAMES, MICHAEL R., JOHNS, RUSSELL C., & PELOWITZ, DENISE B. THE MCNPX MONTE CARLO RADIATION TRANSPORT CODE. United States.
WATERS, LAURIE S., MCKINNEY, GREGG W., DURKEE, JOE W., FENSIN, MICHAEL L., JAMES, MICHAEL R., JOHNS, RUSSELL C., and PELOWITZ, DENISE B. Wed .
"THE MCNPX MONTE CARLO RADIATION TRANSPORT CODE". United States.
doi:. https://www.osti.gov/servlets/purl/1000501.
@article{osti_1000501,
title = {THE MCNPX MONTE CARLO RADIATION TRANSPORT CODE},
author = {WATERS, LAURIE S. and MCKINNEY, GREGG W. and DURKEE, JOE W. and FENSIN, MICHAEL L. and JAMES, MICHAEL R. and JOHNS, RUSSELL C. and PELOWITZ, DENISE B.},
abstractNote = {MCNPX (Monte Carlo NParticle eXtended) is a generalpurpose Monte Carlo radiation transport code with threedimensional geometry and continuousenergy transport of 34 particles and light ions. It contains flexible source and tally options, interactive graphics, and support for both sequential and multiprocessing computer platforms. MCNPX is based on MCNP4B, and has been upgraded to most MCNP5 capabilities. MCNP is a highly stable code tracking neutrons, photons and electrons, and using evaluated nuclear data libraries for lowenergy interaction probabilities. MCNPX has extended this base to a comprehensive set of particles and light ions, with heavy ion transport in development. Models have been included to calculate interaction probabilities when libraries are not available. Recent additions focus on the time evolution of residual nuclei decay, allowing calculation of transmutation and delayed particle emission. MCNPX is now a code of great dynamic range, and the excellent neutronics capabilities allow new opportunities to simulate devices of interest to experimental particle physics; particularly calorimetry. This paper describes the capabilities of the current MCNPX version 2.6.C, and also discusses ongoing code development.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jan 10 00:00:00 EST 2007},
month = {Wed Jan 10 00:00:00 EST 2007}
}

MCNPX (Monte Carlo NParticle eXtended) is a generalpurpose Monte Carlo radiation transport code with threedimensional geometry and continuousenergy transport of 34 particles and light ions. It contains flexible source and tally options, interactive graphics, and support for both sequential and multiprocessing computer platforms. MCNPX is based on MCNP4c and has been upgraded to most MCNP5 capabilities. MCNP is a highly stable code tracking neutrons, photons and electrons, and using evaluated nuclear data libraries for lowenergy interaction probabilities. MCNPX has extended this base to a comprehensive set of particles and light ions, with heavy ion transport in development. Models have beenmore »

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