Development and Validation of a Probabilistic Risk Assessment Model for a Generic Modular High Temperature Gas-Cooled Reactor

This study looks to develop and validate a probabilistic risk assessment (PRA) model for the modular high temperature gas-cooled reactor (MHTGR) using INL’s Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) software. Validation against a General Atomics design involves matching event and fault trees to historical frequencies, with a goal of under 15% difference. The research aims to deliver a reliable PRA model to assess the safety of MHTGRs for use within high-temperature industrial applications.

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OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Published
2024-09-12
Primary Topic
Nuclear reactor physics and engineering
Type
article

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article

Development and Validation of a Probabilistic Risk Assessment Model for a Generic Modular High Temperature Gas-Cooled Reactor

Cody Parkinson
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Nuclear reactor physics and engineering
article

Development and Validation of a Probabilistic Risk Assessment Model for a Generic Modular High Temperature Gas-Cooled Reactor

Cody Parkinson
article en

Abstract

This study looks to develop and validate a probabilistic risk assessment (PRA) model for the modular high temperature gas-cooled reactor (MHTGR) using INL’s Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) software. Validation against a General Atomics design involves matching event and fault trees to historical frequencies, with a goal of under 15% difference. The research aims to deliver a reliable PRA model to assess the safety of MHTGRs for use within high-temperature industrial applications.

OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Idaho National Laboratory (US)
U.S. Department of Energy, Battelle, Idaho Operations Office, U.S. Department of Energy
Affordable and clean energy
Nuclear reactor physics and engineering
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