Advanced Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Demonstration

Curtis Smith ; Steven Prescott ; Tony Koonce

关键词: PRA;    safety;    SMR;   

DOI  :  10.2172/1149017
RP-ID  :  INL/EXT-14-31876
PID  :  OSTI ID: 1149017

学科分类：数学（综合）

美国|英语

来源: SciTech Connect

【 摘 要 】

A key area of the Advanced Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) strategy is the development of methodologies and tools that will be used to predict the safety, security, safeguards, performance, and deployment viability of SMRs. The goal of the SMR PRA activity will be to develop quantitative methods and tools and the associated analysis framework for assessing a variety of risks. Development and implementation of SMR-focused safety assessment methods may require new analytic methods or adaptation of traditional methods to the advanced design and operational features of SMRs. We will need to move beyond the current limitations such as static, logic-based models in order to provide more integrated, scenario-based models based upon predictive modeling which are tied to causal factors. The development of SMR-specific safety models for margin determination will provide a safety case that describes potential accidents, design options (including postulated controls), and supports licensing activities by providing a technical basis for the safety envelope. This report documents the progress that was made to implement the PRA framework, specifically by way of demonstration of an advanced 3D approach to representing, quantifying and understanding flooding risks to a nuclear power plant.