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Title: MCNP6 Fission Multiplicity with FMULT Card

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.
Authors:
 [1] ;  [1] ;  [1] ;  [1] ;  [1]
  1. Los Alamos National Laboratory
Publication Date:
OSTI Identifier:
1044098
Report Number(s):
LA-UR-12-22273
TRN: US1203329
DOE Contract Number:
AC52-06NA25396
Resource Type:
Conference
Resource Relation:
Conference: 2012 ANS Summer Meeting ; 2012-06-24 - 2012-06-28 ; Chicago, Illinois, United States
Research Org:
Los Alamos National Laboratory (LANL)
Sponsoring Org:
DOE/LANL
Country of Publication:
United States
Language:
English
Subject:
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; BENCHMARKS; FISSION; MULTIPLICITY; THERMAL NEUTRONS