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Title: A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment

Abstract

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 inmore » 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.« less

Authors:
; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy
OSTI Identifier:
1367862
DOE Contract Number:
AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Conference: 24th International Conference on Nuclear Engineering (ICONE 24), 06/26/16 - 06/30/16, Charlotte, NC, US
Country of Publication:
United States
Language:
English

Citation Formats

Grabaskas, Dave, Brunett, Acacia J., and Bucknor, Matthew. A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment. United States: N. p., 2016. Web. doi:10.1115/ICONE24-60760.
Grabaskas, Dave, Brunett, Acacia J., & Bucknor, Matthew. A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment. United States. doi:10.1115/ICONE24-60760.
Grabaskas, Dave, Brunett, Acacia J., and Bucknor, Matthew. Sun . "A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment". United States. doi:10.1115/ICONE24-60760. https://www.osti.gov/servlets/purl/1367862.
@article{osti_1367862,
title = {A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment},
author = {Grabaskas, Dave and Brunett, Acacia J. and Bucknor, Matthew},
abstractNote = {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.},
doi = {10.1115/ICONE24-60760},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jun 26 00:00:00 EDT 2016},
month = {Sun Jun 26 00:00:00 EDT 2016}
}

Conference:
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