Validation of nuclear criticality safety software and 27 energy group ENDF/B-IV cross sections. Revision 1

Technical Report · Mon Jan 01 00:00:00 EST 1996

DOI:https://doi.org/10.2172/195744· OSTI ID:195744

Lee, Jr, B L ^[1]; D`Aquila, D M ^[2]

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1. Battelle, Columbus, OH (United States)
2. Lockheed Martin Utility Services, Inc., Oak Ridge, TN (United States)

The original validation report, POEF-T-3636, was documented in August 1994. The document was based on calculations that were executed during June through August 1992. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This revision is written to clarify the margin of safety being used at Portsmouth for nuclear criticality safety calculations. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Lockheed Martin Nuclear Criticality Safety Software. The first portion of the document outlines basic information in regard to validation of NCSS using ENDF/B-IV 27-group cross sections on the IBM3090 at ORNL. A basic discussion of the NCSS system is provided, some discussion on the validation database and validation in general. Then follows a detailed description of the statistical analysis which was applied. The results of this validation indicate that the NCSS software may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant. For calculations of Portsmouth systems using the specified codes and systems covered by this validation, a maximum k{sub eff} including 2{sigma} of 0.9605 or lower shall be considered as subcritical to ensure a calculational margin of safety of 0.02. The validation of NCSS on the IBM 3090 at ORNL was extended to include NCSS on the IBM 3090 at K-25.

• Research Organization: Lockheed Martin Utility Services, Inc., Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-84OT21400
• OSTI ID: 195744
• Report Number(s): POEF-T--3636-Rev.1; ON: DE96005813
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
42 ENGINEERING
99 GENERAL AND MISCELLANEOUS
COMPUTER CODES
CRITICALITY
ENRICHED URANIUM
MULTIPLICATION FACTORS
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
PORTSMOUTH GASEOUS DIFFUSION PLANT
SAFETY ANALYSIS
VALIDATION