Published June 18, 2012 | Version v1
Report Metadata-only

MCNP6 Fission Multiplicity with FMULT Card

Creators

  • 1. Los Alamos National Laboratory, NM (United States)

Description

With the merger of MCNPX and MCNP5 into MCNP6, MCNP6 now provides all the capabilities of both codes allowing the user to access all the fission multiplicity data sets. Detailed in this paper is: (1) the new FMULT card capabilities for accessing these different data sets; (2) benchmark calculations, as compared to experiment, detailing the results of selecting these separate data sets for thermal neutron induced fission on U-235.

Additional details

Identifiers

URL
https://www.osti.gov/servlets/purl/1044098/;

Publishing Information

Imprint Pagination
25 p.
Report number
LA-UR--12-22273

Conference

Title
International Congress on Advances in Nuclear Power Plants
Acronym
ICAPP '12
Dates
24-28 Jun 2012
Place
Chicago, IL (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
43119367
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BENCHMARKS; FISSION; MULTIPLICITY; THERMAL NEUTRONS
Descriptors DEC
BARYONS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NEUTRONS; NUCLEAR REACTIONS; NUCLEONS

Optional Information

Contract/Grant/Project number
AC52-06NA25396
Funding organization
DOE/LANL (United States)