MatMCNP V. 3.0

Software · Mon Oct 19 00:00:00 EDT 2015

OSTI ID:1336822

A code for generating MCNP material cards (MatMCNP) has been written and verified for naturally occurring, stable isotopes. 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.

• Short Name / Acronym: MATMCNP; 003787MLTPL00
• Version: 00
• Programming Language(s): Medium: X; OS: Windows 7 OS, UNIX, Linux; Compatibility: Multiplatform
• Research Organization: Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA (United States)
• Sponsoring Organization: USDOE
• Contributing Organization: K. Russell DePriest Karen C. Saavedra
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 1336822
• Country of Origin: United States