Published 2012 | Version v1
Miscellaneous Open

Analysis of long-term DHR System Performance for a LMR

  • 1. ENEA, Bologna (Italy)

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

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Part of:
Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs. Presentations

Additional details

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)