MCNP5 Criticality Validation and Bias for Intermediate Enriched Uranium Systems

Technical Report · Thu Dec 10 00:00:00 EST 2009

DOI:https://doi.org/10.2172/969690· OSTI ID:969690

Finfrock, S. H. ^[1]

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1. CH2M HILL Plateau Remediation Company (CH2M HILL), Richland, WA (United States)

The purpose of this analysis is to validate the Monte Carlo N-Particle 5 (MCNP5) code Version 1.40 (LA-UR-03-1987, 2005) and its cross-section database for k-code calculations of intermediate enriched uranium systems on INTEL^® processor based PC's running any version of the WINDOWS operating system. Configurations with intermediate enriched uranium were modeled with the moderator range of 39≤HlFissile≤1438. See Table 2-1 for brief descriptions of selected cases and Table 3-1 for the range of applicability for this validation. A total of 167 input cases were evaluated including bare and reflected systems in a single body or arrays. The 167 cases were taken directly from the previous (Version 4C [Lan 2005]) validation database. Section 2.0 list data used to calculate k-effective (k_eff) for the 167 experimental criticality benchmark cases using the MCNP5 code v1.40 and its cross-section database. Appendix B lists the MCNP cross-section database entries validated for use in evaluating the intermediate enriched uranium systems for criticality safety. The dimensions and atom densities for the intermediate enriched uranium experiments were taken from NEA/NSC/DOC(95)03, September 2005, which will be referred to as the benchmark handbook throughout the report. For these input values, the experimental benchmark k_eff is approximately 1.0. The MCNP validation computer runs ran to an accuracy of approximately ±0.001. For the cases where the reported benchmark k_effwas not equal to 1.0000 the MCNP calculational results were normalized. The difference between the MCNP validation computer runs and the experimentally measured k_eff is the MCNP5 v1.40 bias. The USLSTATS code (ORNL 1998) was utilized to perform the statistical analysis and generate an acceptable maximum k_eff limit for calculations of the intermediate enriched uranium type systems.

• Research Organization: CH2M HILL Plateau Remediation Company (CH2M HILL), Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC06-08RL14788
• OSTI ID: 969690
• Report Number(s): CHPRC-00455-Rev-0; PRC-EDC-09-43945; TRN: US1000409
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
97 MATHEMATICS AND COMPUTING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
MODERATELY ENRICHED URANIUM
MONTE CARLO METHOD
VALIDATION
CRITICALITY
SAFETY ANALYSIS
ACCURACY
BENCHMARKS
CROSS SECTIONS
Nuclear Criticality Safety Program (NCSP)
Criticality
Monte Carlo Method
K-effective
K-eff
Enrichment
Enriched Uranium
INTEL
INTEL Processor
MCNP5