Published 1975 | Version v1
Book

The relationship between reliability and safety in nuclear power plants

Creators

  • 1. Pollution Prevention (Consultants) Ltd., Crawley (UK)

Description

This paper is concerned primarily with the problem of taking account of the relationship between reliability and safety at the conceptual design stage. The relationship between availability and safety is discussed and a composite set of quantitative criteria, in a form suitable for use in the design stage, is derived. This set has been used as a basis for the studies employed for illustrative purposes in this paper. A method is described by which reliability engineering techniques can be applied to reactor design at the conceptual stage in order to clarify the more important safety aspects. By the use of this method it is possible to determine the reliability which will be required from each of the major protection systems (i.e. reactor shutdown, core cooling and containment) and from certain critical structures in order that the reactor should meet a given set of safety criteria, specified in quantitative terms. The application of this method to the case of an SGHWR is described. Possible ways of reducing the reliability required from the reactor protection systems are discussed. (author)

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna
ISBN
92-0-050075-7
Imprint Title
Reliability of nuclear power plants
Imprint Pagination
p. 491-502.
Series
Proceedings series.

Conference

Title
Symposium on the reliability of nuclear power plants.
Dates
14 Apr 1975.
Place
Innsbruck, Austria.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
7237721
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AVAILABILITY; NUCLEAR POWER PLANTS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIABILITY; SGHWR REACTOR
Descriptors DEC
ENRICHED URANIUM REACTORS; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS

Optional Information

Secondary number(s)
IAEA-SM--195/54.