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Development of phenomena identification and ranking table for Westinghouse lead fast reactor’s safety

Journal Article · · Progress in Nuclear Energy
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The Westinghouse Lead-cooled Fast Reactor (LFR) is a medium-size, passively safe, economic, Gen-IV nuclear reactor. An important effort within the Westinghouse LFR program is the development of the safety analysis methodology, which comprises computer code development, model development, and experimental testing. A key initial task associated with the development of the safety analysis methodology is the identification of processes and phenomena that affect the plant's capability to meet selected safety performance indicators. This is accomplished through the development of a Phenomena Identification and Ranking Table (PIRT) for selected accident scenarios which, for this specific PIRT effort, included selected postulated design basis accidents and hypothetical beyond design basis accidents in LFRs. This paper describes the role of PIRT in the development of the Westinghouse LFR safety analysis methodology and the process used in the PIRT development. Specifically, the Westinghouse LFR PIRT assessed importance of pertinent phenomena and identified gaps in their knowledge-base by evaluating current modeling capabilities and data available for validation. The ultimate goal was to provide guidance on computer code development and validation efforts and to prioritize testing to support LFR design and licensing. The key phenomena and processes that are deemed highly important for the safety performance indicators, but for which the state of knowledge is low, are presented. The testing program and analyses development are planned to address significant phenomena in the PIRT.
Research Organization:
Argonne National Laboratory (ANL)
Sponsoring Organization:
USDOE Office of Technology Transitions (OTT)
DOE Contract Number:
AC02-06CH11357
OSTI ID:
1788199
Journal Information:
Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Vol. 131; ISSN 0149-1970
Country of Publication:
United States
Language:
English

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Lead fast reactor
PIRT