Validation of KENO-Based Criticality Calculations at Rocky Flats
In the absence of experimental data, it is necessary to rely on computer-based computational methods in evaluating the criticality condition of a nuclear system. The validity of the computer codes is established in a two-part procedure as outlined in ANSI/ANS 8.1. The first step, usually the responsibility of the code developer, involves verification that the algorithmic structure of the code is performing the intended mathematical operations correctly. The second step involves an assessment of the code's ability to realistically portray the governing physical processes in question. This is accomplished by determining the code's bias, or systematic error, through a comparison of computational results to accepted values obtained experimentally. In this paper, the authors discuss the validation process for KENO and the Hansen-Roach cross sections in use at EG and G Rocky Flats. The validation process at Rocky Flats consists of both global and local techniques. The global validation resulted in a maximum keff limit of 0.95 for the limiting-accident scenarios of a criticality evaluation.
- Research Organization:
- EG and G Rocky Flats, Inc., Golden, CO (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 6956924
- Report Number(s):
- CONF-920606-; CODEN: TANSA
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 65; Conference: American Nuclear Society Annual Meeting , Boston, MA (United States), 7-12 Jun 1992; ISSN 0003-018X
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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Validation of KENO Based Criticality Calculations at Rocky Flats
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Related Subjects
97 MATHEMATICS AND COMPUTING
FISSIONABLE MATERIALS
CRITICALITY
K CODES
ALGORITHMS
BENCHMARKS
CALCULATION METHODS
CROSS SECTIONS
MULTIPLICATION FACTORS
ROCKY FLATS PLANT
SUBCRITICALITY
VALIDATION
VERIFICATION
COMPUTER CODES
MATERIALS
MATHEMATICAL LOGIC
NATIONAL ORGANIZATIONS
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
Nuclear Criticality Safety Program (NCSP)
ANSI/ANS 8.1
Computer-Based Computational Methods
Nuclear System Criticality Condition Evaluation
Validation
420203* - Engineering- Handling Equipment & Procedures