Development of methods for internal event (level 1) multi-unit PRA
Creators
- 1. Central Research Institute of Electric Power Industry, Nuclear Risk Research Center, Risk Assessment Research Team, Yokosuka, Kanagawa (Japan)
Description
On March 11, 2011, the Fukushima Daiichi nuclear accident, triggered by the earthquake and tsunami, revealed the significant risk at a site with multiple nuclear power reactors. Since then, multi-unit probabilistic risk assessment (MUPRA) has attracted increased attention. Although several research groups have proposed frameworks for MUPRA, only a few MUPRAs have been conducted in the industry. This report provides an evaluation framework for an internal-event Level 1 MUPRA by extending single-unit probabilistic risk assessment (SUPRA) models to an MUPRA model. The proposed MUPRA framework is based on conventional SUPRA event tree/fault tree (ET/FT) and minimal cutset methods. The framework provides a procedure for extending the existing SUPRA models to an MUPRA model. In addition, the framework provides methods for (1) inter-unit common-cause failure analysis, (2) multi-unit human reliability analysis, and (3) multi-unit accident sequence development and frequency quantification. This report provides an example of MUPRA implementation using the framework. The example is a case study of two advanced boiling water reactors with a loss of off-site power as the initiating event, and the feasibility of the framework is confirmed through this case study. (author)
Availability note (English)
Available from https://criepi.denken.or.jp/hokokusho/pb/reportDetail?reportNoUkCode=NR22003Additional details
Additional titles
- Original title (Japanese)
- 内的事象レベル1 マルチユニットPRA手法の開発
Publishing Information
- Imprint Pagination
- 128 p.
- Report number
- CRIEPI--NR22003
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 55018677
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ATWS; BWR TYPE REACTORS; FAILURE MODE ANALYSIS; FAILURES; FAULT TREE ANALYSIS; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; HUMAN FACTORS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR CORE DISRUPTION; RELIABILITY; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR SITES; REACTORS; SEVERE ACCIDENTS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 39 refs., 42 figs., 16 tabs.