MCNP Calculations for Russian Criticality-Safety Benchmarks
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
The current edition of the International Handbook of Evaluated Criticality Safety Benchmark Experiments contains evaluations of 20 critical experiments performed and evaluated by the Institute for Experimental Physics of the Russian Federal Nuclear Center (VNIIEF) at Arzamas-16 and 16 critical experiments performed and evaluated by the Institute for Technical Physics of the Russian Federal Nuclear Center (VNIITF) at Chelyabinsk-70. These fast-spectrum experiments are of particular interest for data testing of ENDF/B-VI because they contain uranium metal systems of intermediate enrichment as well as uranium and plutonium metal systems with reflectors such as graphite, stainless steel, polyethylene, beryllium, and beryllium oxide. This paper presents the first published results for such systems using cross-section libraries based on ENDF/B-VI.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 515563
- Report Number(s):
- LA-UR-96-3789; CONF-970926-1; ON: DE97002342; TRN: 97:015828
- Resource Relation:
- Conference: American Nuclear Society (ANS) Topical Meeting on Criticality Safety Challenges in the Next Decade, Experiments, Benchmarks, and Validation, Chelan, WA (United States), 7-11 Sep 1997; Other Information: PBD: [1996]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
97 MATHEMATICS AND COMPUTING
NUCLEAR DATA COLLECTIONS
CRITICALITY
BENCHMARKS
COMPUTER CALCULATIONS
TESTING
MULTIPLICATION FACTORS
Nuclear Criticality Safety Program (NCSP)
Monte Carlo N-Particle (MCNP)
Intermediate-Enriched Uranium (IEU)
Highly Enriched Uranium (HEU)
Evaluated Nuclear Data File (ENDF)
Cross Section Libraries