Published September 1, 2014
| Version v1
Report
MatMCNP: A Code for Producing Material Cards for MCNP
Creators
- 1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- 2. American Structurepoint, Inc., Indianapolis, IN (United States)
Description
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.
Availability note (English)
Available from http://prod.sandia.gov/sand_doc/2014/1417693.pdf; PURL: http://www.osti.gov/servlets/purl/1323135/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 136 p.
- Report number
- SAND--2014-17693
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 48002589
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BORON; DENSITY; GAMMA RADIATION; LITHIUM; M CODES; NEUTRAL-PARTICLE TRANSPORT; NEUTRONS; RADIATION DOSES; STABLE ISOTOPES; URANIUM
- Descriptors DEC
- ACTINIDES; ALKALI METALS; BARYONS; COMPUTER CODES; DOSES; ELECTROMAGNETIC RADIATION; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; HADRONS; IONIZING RADIATIONS; ISOTOPES; METALS; NUCLEONS; PHYSICAL PROPERTIES; RADIATION TRANSPORT; RADIATIONS; SEMIMETALS
Optional Information
- Contract/Grant/Project number
- AC04-94AL85000
- Funding organization
- USDOE National Nuclear Security Administration (NNSA) (United States)
- Secondary number(s)
- OSTIID--1323135