Criticality Safety Validation of SCALE 6.1 with ENDF/B-VII.0 Libraries
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
ANSI/ANS-8.1-1998;2007, Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors, and ANSI/ANS-8.24-2007, Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations, require validation of a computer code and the associated data through benchmark evaluations based on physical experiments. The performance of the code and data are validated by comparing the calculated and the benchmark results. A SCALE procedure has been established to generate a Verified, Archived Library of Inputs and Data (VALID). This procedure provides a framework for preparing, peer reviewing, and controlling models and data sets derived from benchmark definitions so that the models and data can be used with confidence. The procedure ensures that the models and data were correctly generated using appropriate references with documented checks and reviews. Configuration management is implemented to prevent inadvertent modification of the models and data or inclusion of models that have not been subjected to the rigorous review process. VALID entries for criticality safety are based on critical experiments documented in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE). The findings of a criticality safety validation of SCALE 6.1 utilizing the benchmark models vetted in the VALID library at Oak Ridge National Laboratory are summarized here.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1044656
- Journal Information:
- Transactions of the American Nuclear Society, Conference: 2012 ANS Annual Meeting , Chicago, IL (United States, 24-28 Jun 2012; ISSN 0003-018X
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
97 MATHEMATICS AND COMPUTING
BENCHMARKS
COMPUTER CODES
CONFIGURATION
CRITICALITY
FISSIONABLE MATERIALS
MANAGEMENT
MANUALS
MODIFICATIONS
NEUTRON TRANSPORT
ORNL
PERFORMANCE
SAFETY
VALIDATION
Nuclear Criticality Safety Program (NCSP)
ANSI/ANS-8.1-1998
2007
SCALE
Verified
Archived Library of Inputs and Data (VALID)
International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE)