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Title: MCNP6 Fission Multiplicity with FMULT Card

Conference ·
OSTI ID:1044098

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.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
DOE/LANL
DOE Contract Number:
AC52-06NA25396
OSTI ID:
1044098
Report Number(s):
LA-UR-12-22273; TRN: US1203329
Resource Relation:
Conference: 2012 ANS Summer Meeting ; 2012-06-24 - 2012-06-28 ; Chicago, Illinois, United States
Country of Publication:
United States
Language:
English