Criticality Safety Validation of SCALE 6.1 with ENDF/B-VII.0 Libraries
Description/Abstract
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.
| Creator/Author: | Marshall, William BJ J [ORNL] ; Rearden, Bradley T [ORNL] |
|---|---|
| Publication Date: | 2012 Jan 01 |
| OSTI Identifier: | OSTI ID: 1044656 |
| DOE Contract Number: | DE-AC05-00OR22725 |
| Other Number(s): | Other: DP0902090; DPDP097; TRN: US1203461 |
| Resource Type: | Conference |
| Resource Relation: | Conference: 2012 ANS Annual Meeting, Chicago, IL, USA, 20120624, 20120628 |
| Research Org: | Oak Ridge National Laboratory (ORNL) |
| Sponsoring Org: | NNSA USDOE - National Nuclear Security Administration (NNSA) |
| Subject: | 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BENCHMARKS; COMPUTER CODES; CONFIGURATION; CRITICALITY; FISSIONABLE MATERIALS; MANAGEMENT; MANUALS; MODIFICATIONS; NEUTRON TRANSPORT; ORNL; PERFORMANCE; SAFETY; VALIDATION |
| Country of Publication: | United States |
| Language: | English |
| Format: | Size: 456-460 |
| Update Date: | 2013 Jun 06 |
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