Probabilistic Safety Assessment of Multi Unit Site of Nuclear Power Plant
Creators
- 1. Pakistan Nuclear Regulatory Authority, Karachi (Pakistan)
Description
It is a common practice around the world to install multiple units of nuclear power plants on a single site taking advantage of common intake cooling structure, shared components, etc. The accident at the Fukushima Daiichi nuclear power plant highlighted the risks from multiple nuclear reactor unit accidents at a site urging the nuclear community to analyse the multi-unit (MU) risks to avoid re-occurrence of similar accidents. A multi-unit site PSA model has to deal with the dependencies existing between the units on that site. Common cause models used in traditional single unit PSAs were originally developed for arrays of redundant components within a single nuclear power plant. If there are identical, redundant components and systems that are replicated on multiple reactor unit, the common cause failure (CCF) that may impact components on different units needs to be considered. This study is conducted to identify main risk contributors that delineate multi-unit risk from single-unit risks. A case study is performed based on full power level-I PSA model to identify plant vulnerabilities considering risk from shared components, common-cause failure of multi structures and components to calculate multi-unit core damage frequency (MUCDF) based on multi-unit initiating events (MUIEs).
Files
ID66.pdf
Files
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System files
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Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs
- Imprint Pagination
- 7 p.
- Report number
- STI/PUB/2108
Conference
- Title
- International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs
- Dates
- 18-21 Oct 2022
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DAMAGE; FAILURE MODE ANALYSIS; FAILURES; FUKUSHIMA ACCIDENT ARCHIVE; FUKUSHIMA ACCIDENT DATA; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; FUKUSHIMA-1 REACTOR; MELTDOWN; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; RCIC SYSTEMS; REACTOR ACCIDENTS; RISK ASSESSMENT; SAFETY ANALYSIS; UNITS; VULNERABILITY
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BWR TYPE REACTORS; CALCULATION METHODS; COOLING SYSTEMS; DATASETS; DOCUMENT TYPES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FUKUSHIMA ACCIDENT ARCHIVE; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SITES; REACTORS; SEVERE ACCIDENTS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs., 1 tab., 3 figs.
- Secondary number(s)
- IAEA-CN--308(SUPPLEMENTARY FILES)