MCNP Version 6.2 Release Notes

doi:10.2172/1419730

Title: MCNP Version 6.2 Release Notes

Full Record
Other Related Research

You are accessing a document from the Department of Energy's (DOE) OSTI.GOV. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service.

Visit OSTI to utilize additional information resources in energy science and technology.

Abstract

Monte Carlo N-Particle or MCNP ^® is a general-purpose Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. This MCNP Version 6.2 follows the MCNP6.1.1 beta version and has been released in order to provide the radiation transport community with the latest feature developments and bug fixes for MCNP. Since the last release of MCNP major work has been conducted to improve the code base, add features, and provide tools to facilitate ease of use of MCNP version 6.2 as well as the analysis of results. These release notes serve as a general guide for the new/improved physics, source, data, tallies, unstructured mesh, code enhancements and tools. For more detailed information on each of the topics, please refer to the appropriate references or the user manual which can be found at http://mcnp.lanl.gov. This release of MCNP version 6.2 contains 39 new features in addition to 172 bug fixes and code enhancements. There are still some 33 known issues the user should familiarize themselves with (see Appendix).

Authors:

Werner, Christopher John ^[1]; Bull, Jeffrey S. ^[1]; Solomon, C. J. ^[1]; Brown, Forrest B. ^[1]; McKinney, Gregg Walter ^[1]; Rising, Michael Evan ^[1]; Dixon, David A. ^[1]; Martz, Roger Lee ^[1]; Hughes, Henry G. ^[1]; Cox, Lawrence James ^[1]; Zukaitis, Anthony J. ^[1]; Armstrong, J. C. ^[1]; Forster, Robert Arthur ^[1]; Casswell, Laura ^[1]

Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Publication Date:: 2018-02-05

Research Org.:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA), Office of Defense Programs (DP) (NA-10)

OSTI Identifier:: 1419730

Report Number(s):: LA-UR-18-20808

DOE Contract Number:: AC52-06NA25396

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; MCNP

Citation Formats


                    Werner, Christopher John, Bull, Jeffrey S., Solomon, C. J., Brown, Forrest B., McKinney, Gregg Walter, Rising, Michael Evan, Dixon, David A., Martz, Roger Lee, Hughes, Henry G., Cox, Lawrence James, Zukaitis, Anthony J., Armstrong, J. C., Forster, Robert Arthur, and Casswell, Laura. MCNP Version 6.2 Release Notes.  United States: N. p., 2018. 
        Web.  doi:10.2172/1419730.

Copy to clipboard


                    Werner, Christopher John, Bull, Jeffrey S., Solomon, C. J., Brown, Forrest B., McKinney, Gregg Walter, Rising, Michael Evan, Dixon, David A., Martz, Roger Lee, Hughes, Henry G., Cox, Lawrence James, Zukaitis, Anthony J., Armstrong, J. C., Forster, Robert Arthur, & Casswell, Laura. MCNP Version 6.2 Release Notes.  United States.  doi:10.2172/1419730.

Copy to clipboard


                    Werner, Christopher John, Bull, Jeffrey S., Solomon, C. J., Brown, Forrest B., McKinney, Gregg Walter, Rising, Michael Evan, Dixon, David A., Martz, Roger Lee, Hughes, Henry G., Cox, Lawrence James, Zukaitis, Anthony J., Armstrong, J. C., Forster, Robert Arthur, and Casswell, Laura. Mon .  
        "MCNP Version 6.2 Release Notes".  United States.  doi:10.2172/1419730.  https://www.osti.gov/servlets/purl/1419730.

Copy to clipboard


                    
@article{osti_1419730,

  title        = {MCNP Version 6.2 Release Notes},

  author       = {Werner, Christopher John and Bull, Jeffrey S. and Solomon, C. J. and Brown, Forrest B. and McKinney, Gregg Walter and Rising, Michael Evan and Dixon, David A. and Martz, Roger Lee and Hughes, Henry G. and Cox, Lawrence James and Zukaitis, Anthony J. and Armstrong, J. C. and Forster, Robert Arthur and Casswell, Laura},

  abstractNote = {Monte Carlo N-Particle or MCNP® is a general-purpose Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. This MCNP Version 6.2 follows the MCNP6.1.1 beta version and has been released in order to provide the radiation transport community with the latest feature developments and bug fixes for MCNP. Since the last release of MCNP major work has been conducted to improve the code base, add features, and provide tools to facilitate ease of use of MCNP version 6.2 as well as the analysis of results. These release notes serve as a general guide for the new/improved physics, source, data, tallies, unstructured mesh, code enhancements and tools. For more detailed information on each of the topics, please refer to the appropriate references or the user manual which can be found at http://mcnp.lanl.gov. This release of MCNP version 6.2 contains 39 new features in addition to 172 bug fixes and code enhancements. There are still some 33 known issues the user should familiarize themselves with (see Appendix).},

  doi          = {10.2172/1419730},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2018},

  month        = {2}

}

Copy to clipboard

Technical Report:

View Technical Report

DOI: 10.2172/1419730

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

MCNP (Monte Carlo Neutron Photon) capabilities for nuclear well logging calculations

Conference Forster, R A ; Little, R C ; Briesmeister, J F

The Los Alamos Radiation Transport Code System (LARTCS) consists of state-of-the-art Monte Carlo and discrete ordinates transport codes and data libraries. The general-purpose continuous-energy Monte Carlo code MCNP (Monte Carlo Neutron Photon), part of the LARTCS, provides a computational predictive capability for many applications of interest to the nuclear well logging community. The generalized three-dimensional geometry of MCNP is well suited for borehole-tool models. SABRINA, another component of the LARTCS, is a graphics code that can be used to interactively create a complex MCNP geometry. Users can define many source and tally characteristics with standard MCNP features. The time-dependent capabilitymore »« less
Full Text Available
Physics and Algorithm Enhancements for a Validated MCNP/X Monte Carlo Simulation Tool, Phase VII

Conference McKinney, Gregg W

Currently the US lacks an end-to-end (i.e., source-to-detector) radiation transport simulation code with predictive capability for the broad range of DHS nuclear material detection applications. For example, gaps in the physics, along with inadequate analysis algorithms, make it difficult for Monte Carlo simulations to provide a comprehensive evaluation, design, and optimization of proposed interrogation systems. With the development and implementation of several key physics and algorithm enhancements, along with needed improvements in evaluated data and benchmark measurements, the MCNP/X Monte Carlo codes will provide designers, operators, and systems analysts with a validated tool for developing state-of-the-art active and passive detectionmore »« less
Full Text Available
Verification of MCNP6.2 for Nuclear Criticality Safety Applications

Technical Report Brown, Forrest B. ; Rising, Michael Evan ; Alwin, Jennifer Louise

Several suites of verification/validation benchmark problems were run in early 2017 to verify that the new production release of MCNP6.2 performs correctly for nuclear criticality safety applications (NCS). MCNP6.2 results for several NCS validation suites were compared to the results from MCNP6.1 [1] and MCNP6.1.1 [2]. MCNP6.1 is the production version of MCNP® released in 2013, and MCNP6.1.1 is the update released in 2014. MCNP6.2 includes all of the standard features for NCS calculations that have been available for the past 15 years, along with new features for sensitivity-uncertainty based methods for NCS validation [3]. Results from the benchmark suitesmore »« less
DOI: 10.2172/1356287

Full Text Available
Monte Carlo Techniques for Nuclear Systems - Theory Lectures

Technical Report Brown, Forrest B.

These are lecture notes for a Monte Carlo class given at the University of New Mexico. The following topics are covered: course information; nuclear eng. review & MC; random numbers and sampling; computational geometry; collision physics; tallies and statistics; eigenvalue calculations I; eigenvalue calculations II; eigenvalue calculations III; variance reduction; parallel Monte Carlo; parameter studies; fission matrix and higher eigenmodes; doppler broadening; Monte Carlo depletion; HTGR modeling; coupled MC and T/H calculations; fission energy deposition. Solving particle transport problems with the Monte Carlo method is simple - just simulate the particle behavior. The devil is in the details, however. Thesemore »« less
DOI: 10.2172/1334102

Full Text Available
MCNP capabilities for nuclear well logging calculations

Conference Forster, R A ; Little, R C ; Briesmeister, J F ; ... - IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (USA)

The Los Alamos Radiation Transport Code System (LARTCS) consists of state-of-the-art Monte Carlo and discrete ordinates transport codes and data libraries. This paper discusses how the general-purpose continuous-energy Monte Carlo code MCNP ({und M}onte {und C}arlo {und n}eutron {und p}hoton), part of the LARTCS, provides a computational predictive capability for many applications of interest to the nuclear well logging community. The generalized three-dimensional geometry of MCNP is well suited for borehole-tool models. SABRINA, another component of the LARTCS, is a graphics code that can be used to interactively create a complex MCNP geometry. Users can define many source and tallymore »« less

Similar Records