Additional critical experiments for computer code validation base

Technical Report · Mon Apr 25 00:00:00 EDT 1994

DOI:https://doi.org/10.2172/10186142· OSTI ID:10186142

Elliott, E P; Tollefson, D A; Vornehm, R G

This paper describes the validation, in accordance with ANSI/ANS-8.1-1983(R1988), of KENO V.a using the 27-group ENDF/B-IV cross section library for some neutronic systems containing highly-enriched uranium, carbon, and hydrogen. This constituent combination is present in many packaging applications for the safe transportation of fissile and fissionable materials. The validation has been performed for two separate computational platforms: an IBM 3090 mainframe and an HP 9000 Series 700 workstation, both using the Oak Ridge Y-12 Plant Nuclear Criticality Safety Software (NCSS) code package. Critical experiments performed at the Oak Ridge Critical Experiments Facility in support of the Rover reactor program were identified as having the constitutents desired for this validation as well as sufficient experimental detail to allow accurate construction of KENO V.a calculational models. Calculated values of k{sub eff} for the Rover experiments, which contain uranium, carbon, and hydrogen, are between 1.0012 {+-} 0.0026 and 1.0245 {+-} 0.0023. These experiments can now be added to KENO V.a and other computer code critical experiment data bases which are used for validation and to establish upper limits on calculated values of k{sub eff} for specific applications.

• Research Organization: Oak Ridge Y-12 Plant (Y-12), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 10186142
• Report Number(s): Y/DD-631; ON: DE95000609; TRN: 94:020319
• Resource Relation: Other Information: PBD: 25 Apr 1994
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
K CODES
VALIDATION
FISSIONABLE MATERIALS
CRITICALITY
TRANSPORT
NUCLEAR DATA COLLECTIONS
OR-CEF REACTOR
LIMITING VALUES
MULTIPLICATION FACTORS
CONTAINERS
420203
990200
HANDLING EQUIPMENT AND PROCEDURES
MATHEMATICS AND COMPUTERS