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Title: MatMCNP v. 4.0

Abstract

https://www.osti.gov/doecMatMCNP is a code for generating material cards for the MCNP radiation transport code. The program allows for material specification as either atomic or weight percent (fractions). MatMCNP also permits the specification of enriched lithium, boron, and/or uranium. In addition to producing the material cards for MCNP, the code calculates the atomic (or number) density in atoms/barn-cm as well as the multiplier that should be used to convert neutron and gamma fluences into dose in the material specified.

Developers:
 [1]
  1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Release Date:
Project Type:
Open Source, Publicly Available Repository
Software Type:
Scientific
Programming Languages:
Fortran
Version:
v. 4.0
Licenses:
BSD 3-clause "New" or "Revised" License
Sponsoring Org.:
USDOE

Primary Award/Contract Number:
NA0003525
Code ID:
22907
Site Accession Number:
SCR 1716.1
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Country of Origin:
United States

Citation Formats

Depriest, Kendall, and USDOE. MatMCNP v. 4.0. Computer software. https://www.osti.gov//servlets/purl/1491823. Vers. v. 4.0. USDOE. 16 Jan. 2019. Web. doi:10.11578/dc.20190124.1.
Depriest, Kendall, & USDOE. (2019, January 16). MatMCNP v. 4.0 (Version v. 4.0) [Computer software]. https://www.osti.gov//servlets/purl/1491823. doi:10.11578/dc.20190124.1.
Depriest, Kendall, and USDOE. MatMCNP v. 4.0. Computer software. Version v. 4.0. January 16, 2019. https://www.osti.gov//servlets/purl/1491823. doi:10.11578/dc.20190124.1.
@misc{osti_1491823,
title = {MatMCNP v. 4.0, Version v. 4.0},
author = {Depriest, Kendall and USDOE},
abstractNote = {https://www.osti.gov/doecMatMCNP is a code for generating material cards for the MCNP radiation transport code. The program allows for material specification as either atomic or weight percent (fractions). MatMCNP also permits the specification of enriched lithium, boron, and/or uranium. In addition to producing the material cards for MCNP, the code calculates the atomic (or number) density in atoms/barn-cm as well as the multiplier that should be used to convert neutron and gamma fluences into dose in the material specified.},
url = {https://www.osti.gov//servlets/purl/1491823},
doi = {10.11578/dc.20190124.1},
year = {2019},
month = {1},
note =
}

Software:
Publicly Accessible Repository
https://github.com/krdepri/MatMCNP

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