MCNP{trademark} ENDF/B-VI iron benchmark calculations
Conference
·
OSTI ID:10172269
Four iron shielding benchmarks have been calculated for, we believe the first time, with MCNP4A and its new ENDF/B-VI library. These calculations are part of the Hiroshima/Nagasaki dose re-evaluation for the National Academy of Sciences and the Defense Nuclear Agency. We believe these calculations are significant because they validate MCNP and the new ENDF/B-VI libraries. These calculations are compared to ENDF/B-V, experiment, and in some cases the recommended MCNP data library (a T-2 evaluation) and ENDF/IV.
- Research Organization:
- Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 10172269
- Report Number(s):
- LA-UR-94-2520; CONF-941102-14; ON: DE94016165
- Resource Relation:
- Conference: Winter meeting of the American Nuclear Society (ANS),Washington, DC (United States),13-18 Nov 1994; Other Information: PBD: [1994]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
RADIATION TRANSPORT
M CODES
IRON
MONTE CARLO METHOD
NEUTRON TRANSPORT
PHOTON TRANSPORT
TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
SHIELDING MATERIALS
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990200
RADIATION PHYSICS
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99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
RADIATION TRANSPORT
M CODES
IRON
MONTE CARLO METHOD
NEUTRON TRANSPORT
PHOTON TRANSPORT
TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
SHIELDING MATERIALS
663600
990200
RADIATION PHYSICS
MATHEMATICS AND COMPUTERS