Analysis of long-term DHR System Performance for a LMR
Description
Conclusions: • The demonstration of the «Non credibility» of the situation related to the long - term loss of DHR function is organized through: – Probabilistic assessment approach; – Demonstration of negligible risk; – Probabilistic goals. • Results show the inadequacy of design measures to meet the safety requirement of 10-7/reactor year: – System redundancies and configuration. • Results subject to the assumptions taken in the analysis: – Lack of statistically reliable data for LMRs; – Level of definition of the systems, which are not yet established; – Conservative value of the frequency of the initiator, corresponding to the normal shutdown. • Results show the relevance of CCFs; • Other provisions that could justify the "practical elimination": – Diversification of components to cope with CCFs; – DHR function through vault cooling
Files
45091379.pdf
Files
(1.4 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:88005d09b50ac4374f591eaa99682e8d
|
1.4 MB | Preview Download |
Additional details
Identifiers
Publishing Information
- Imprint Title
- Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs. Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 20 p.
- Report number
- IAEA-TM--42704(presentations)
Conference
- Title
- Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs
- Dates
- 19-23 Mar 2012
- Place
- Dresden (Germany)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45091379
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; COOLING; DESIGN; HAZARDS; PROBABILISTIC ESTIMATION; SAFETY; SHUTDOWN
- Descriptors DEC
- CALCULATION METHODS; REMOVAL
Optional Information
- Notes
- Imprint:Conducted within the framework of IAEA Nuclear Energy Department#Right Single Quotation Mark#s Technical Working Group on Fast Reactors (TWG-FR)