Validation of nuclear criticality safety software and 27 energy group ENDF/B-IV cross sections. Revision 1
Creators
- 1. Battelle, Columbus, OH (United States)
- 2. Lockheed Martin Utility Services, Inc., Oak Ridge, TN (United States)
Description
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 keff including 2σ 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
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE96005813; NTIS; US Govt. Printing Office Dep.Files
27048011.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 120 p.
- Report number
- POEF-T--3636-Rev.1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27048011
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- COMPUTER CODES; CRITICALITY; ENRICHED URANIUM; MULTIPLICATION FACTORS; NUCLEAR DATA COLLECTIONS; PORTSMOUTH GASEOUS DIFFUSION PLANT; SAFETY ANALYSIS; VALIDATION
- Descriptors DEC
- ACTINIDES; ELEMENTS; GASEOUS DIFFUSION PLANTS; INDUSTRIAL PLANTS; ISOTOPE ENRICHED MATERIALS; ISOTOPE SEPARATION PLANTS; MATERIALS; METALS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; TESTING; URANIUM; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OT21400
- Funding organization
- USDOE, Washington, DC (United States).