Published 1987 | Version v1
Book

Prospects for use of probabilistic safety criteria

Creators

  • 1. International Atomic Energy Agency, Vienna (Austria)

Description

Design against accidents is so far mainly based on deterministic criteria. Deterministic criteria consist of a set of engineering principles (e.g. defense-in-depth, redundancy, diversity, fail-safe) and design against a set of pre-selected, so-called design base accidents. To analyse the remaining risk and to find optimal ways to reduce risks is called risk management. The management of risks is based on two principles: - risk can be reduced below any given level, however, not to zero, and - the cost of further risk reduction increases with the level of safety achieved. It is thus necessary to find a balanced approach for cost-effective risk reduction. There are three paths to reduce risk from accidents both for using prevention and mitigation strategies: a) more extended application of engineering principles, b) extension of the set of design base accidents to include more unlikely events, and c) analysis and quantification of the remaining risk, and risk reduction based on decision criteria (i.e. probabilistic safety criteria). It is clear that all three options have to be followed and that the deterministic approaches (a and b) and the probabilistic approach (c) have to complement each other. The probabilistic approach also provides a rational tool to check on the balance and risk significance of measures taken based on a) or b). This paper concentrates on the probabilistic approach especially as it relates to nuclear plants

Additional details

Publishing Information

Publisher
A.A. Balkema Publishers.
Imprint Place
Accord, MA (USA)
ISBN
90-6191-774-3
Imprint Title
Structural mechanics in reactor technology
Journal Page Range
p. 31-42.

Conference

Title
international conference on structural mechanics in reactor technology.
Acronym
9. SMIRT
Dates
17-21 Aug 1987.
Place
Lausanne (Switzerland).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19076810
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALGORITHMS; FAILURE MODE ANALYSIS; FORECASTING; MANAGEMENT; POWER REACTORS; PROBABILITY; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ASSESSMENT; SPECIFICATIONS
Descriptors DEC
ACCIDENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS