MCNP Calculations for Criticality Safety Benchmarks with ENDF/B-V and ENDF/B-VI Libraries
Conference
·
OSTI ID:97187
- Univ. of Arizona, Tucson, AZ (United States). Department of Nuclear Engineering
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States). Reactor Design and Analysis Group, Technology and Safety Assessment Division
The MCNP Monte Carlo code, in conjunction with its continuous-energy ENDF/B-V and ENDF/B-VI cross-section libraries, has been benchmarked against results from 27 different critical experiments. The predicted values of keff are in excellent agreement with the benchmarks, except for the ENDF/B-V results for solutions of plutonium nitrate and, to a lesser degree, for the ENDF/B-V and ENDF/B-VI results for a bare sphere of 233U.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States). Reactor Design and Analysis Group, Technology and Safety Assessment Division; Univ. of Arizona, Tucson, AZ (United States). Department of Nuclear Engineering
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 97187
- Report Number(s):
- LA-UR-95-1856; CONF-9509100-25; ON: DE95015255; TRN: 95:019264
- Resource Relation:
- Conference: ICNC '95: 5. International Conference on Nuclear Criticality Safety, Albuquerque, NM (United States), 17-22 Sep 1995; Other Information: PBD: [1995]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
CRITICALITY
M CODES
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
CROSS SECTIONS
URANIUM 233
BENCHMARKS
REACTOR SAFETY
Nuclear Criticality Safety Program (NCSP)
Monte Carlo Code
Evaluated Nuclear Data File (ENDF)
Cross-Section Libraries
Highly Enriched Uranium (HEU)
Fast-Spectrum Plutonium Systems
Jemima Experiments
97 MATHEMATICS AND COMPUTING
CRITICALITY
M CODES
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
CROSS SECTIONS
URANIUM 233
BENCHMARKS
REACTOR SAFETY
Nuclear Criticality Safety Program (NCSP)
Monte Carlo Code
Evaluated Nuclear Data File (ENDF)
Cross-Section Libraries
Highly Enriched Uranium (HEU)
Fast-Spectrum Plutonium Systems
Jemima Experiments