Published May 2016 | Version v1
Report

Accident Conditions to be Considered for 'Practical Elimination'. Appendix 4

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Description

A sudden mechanical failure of a single large component in the reactor coolant system (RCS) could initiate an event where reactor cooling would be lost in a short time and a pressure wave or a missile would damage the containment boundary. The defence in depth provisions would not be effective in such situation and an early large radioactive release would follow. This is a very exceptional type of initiating event for which safety systems and safety features are not designed for their mitigation and therefore it needs to be demonstrated that their likelihood would be certainly so low that they can be excluded, i.e. 'practically eliminated', from consideration. This is essential at least for the reactor vessel, which break would eliminate the capability of holding and cooling the core but also the likelihood of pressurizer and steam generator (SG) shell failure need to be shown to be extremely low, or alternatively it needs to be demonstrated that a failure of pressurizer or SG would not lead to unacceptable consequences to the containment

Part of:
Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants

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Publishing Information

ISBN
978-92-0-104116-6
Imprint Title
Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants
Imprint Pagination
88 p.
Journal Page Range
p. 59-64
ISSN
1011-4289
Report number
IAEA-TECDOC--1791

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
47082380
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
CONTAINMENT; FAILURES; RADIATION ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR VESSELS; STEAM GENERATORS
Descriptors DEC
ACCIDENTS; BOILERS; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; REACTOR COMPONENTS; VAPOR GENERATORS

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