GE Hitachi Nuclear Energy (GEH) and Argonne National Laboratory are currently engaged in a joint effort to modernize and develop probabilistic risk assessment (PRA) techniques for advanced non-light water reactors. At a high level the primary outcome of this project will be the development of next-generation PRA methodologies that will enable risk-informed prioritization of safety- and reliability-focused research and development, while also identifying gaps that may be resolved through additional research. A subset of this effort is the development of a reliability database (RDB) methodology to determine applicable reliability data for inclusion in the quantification of the PRA. The RDB method developed during this project seeks to satisfy the requirements of the Data Analysis element of the ASME/ANS Non-LWR PRA standard. The RDB methodology utilizes a relevancy test to examine reliability data and determine whether it is appropriate to include as part of the reliability database for the PRA. The relevancy test compares three component properties to establish the level of similarity to components examined as part of the PRA. These properties include the component function, the component failure modes, and the environment/boundary conditions of the component. The relevancy test is used to gauge the quality of data found in a variety of sources, such as advanced reactor-specific databases, non-advanced reactor nuclear databases, and non-nuclear databases. The RDB also establishes the integration of expert judgment or separate reliability analysis with past reliability data. This paper provides details on the RDB methodology, and includes an example application of the RDB methodology for determining the reliability of the intermediate heat exchanger of a sodium fast reactor. The example explores a variety of reliability data sources, and assesses their applicability for the PRA of interest through the use of the relevancy test.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5002-2
PROCEEDINGS PAPER
A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment
Dave Grabaskas,
Dave Grabaskas
Argonne National Laboratory, Argonne, IL
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Acacia J. Brunett,
Acacia J. Brunett
Argonne National Laboratory, Argonne, IL
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Matthew Bucknor
Matthew Bucknor
Argonne National Laboratory, Argonne, IL
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Dave Grabaskas
Argonne National Laboratory, Argonne, IL
Acacia J. Brunett
Argonne National Laboratory, Argonne, IL
Matthew Bucknor
Argonne National Laboratory, Argonne, IL
Paper No:
ICONE24-60760, V002T06A031; 9 pages
Published Online:
October 25, 2016
Citation
Grabaskas, D, Brunett, AJ, & Bucknor, M. "A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Charlotte, North Carolina, USA. June 26–30, 2016. V002T06A031. ASME. https://doi.org/10.1115/ICONE24-60760
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