Published 2013
| Version v1
Miscellaneous
Development of probabilistic risk assessment model for spent fuel pool
- 1. Japan Nuclear Energy Safety Organization (JNES), Tokyo (Japan)
Description
Japan Nuclear Energy Safety Organization (JNES) has started the development of PRA models for spent fuel pools (SFPs). This development has been inspired by the lessons of the accident of Fukushima Dai-ichi Nuclear Power Station (NPS). We are planning to develop PRA models for SFPs of Japanese typical BWR and PWR plants by the end of March in 2014. In order to identify the necessary information and issues, JNES develops a prototype of PRA models of a Japanese typical BWR5 plant, and performs a preliminary analysis by the end of March in 2013. This Paper describes intermediate results which have been obtained to date. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the PSAM topical conference in Tokyo (PSAM2013)
- Imprint Pagination
- 532 p.
- Journal Page Range
- 7 p.
Conference
- Title
- PSAM topical conference in Tokyo. In light of the Fukushima Dai-ichi accident
- Acronym
- PSAM2013
- Dates
- 14-18 Apr 2013
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 46013708
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COOLING; FAULT TREE ANALYSIS; FLUID INJECTION; FUEL STORAGE POOLS; MAXIMUM CREDIBLE ACCIDENT; POWER LOSSES; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; SAFETY STANDARDS; WATER
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; DESIGN BASIS ACCIDENTS; ENERGY LOSSES; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; LOSSES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; STANDARDS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 figs., 2 tabs.