Published 1975 | Version v1
Book

Use of standard reliability levels in design and safety assessment of in-pile loops

  • 1. Centro Informazioni Studi Esperienze, Milan (Italy)
  • 2. Centro Comune Ricerche, Ispra, Italy
  • 3. Comitato Nazionale per l'Energia Nucleare, Ispra (Italy)

Description

This paper describes a logic-probabilistic analysis technique for a critical design review and safety assessment of in-pile loops. The examples in this paper refer to the analysis performed for the experimental loops already constructed or under construction in the ESSOR reactor of the Joint Research Centre of Ispra, as irradiation facilities for fuel element research and development tests. The proposed technique is based on the classification into categories of components and protective device malfunctions. Such subdivision into categories was agreed upon by the Italian Safety Authority and Euratom JRC, and adopted for the safety assessment of the ESSOR reactor in-pile loops. For each category, the method makes a link with a corresponding malfunction probability range (probability level). This probability level is defined taking into account design, construction, inspection and maintenance criteria as well as periodic controls; therefore the quality level and consequently the reliability level are thus also defined. The analysis is developed in the following stages: (1) definition of the analysis object (top event) and drawing of the relative fault-tree; (2) loop design analysis and preliminary optimization based on logic criteria; (3) classification into categories of the fault-tree primary events; (4) final loop design analysis and optimization based on defined component quality requirements. Stages 2 and 4 are quite different since stage 2 mainly consists of a redundance optimization, while stage 4 acts on the component quality level in such a way that each minimum cut-set leading to the top has an acceptable probability level. During analysis development, use is made of computer codes which, among other things enable the verification of fault-tree logic makeup, the listing of the minimum cut-sets with and without event categorization, and the evaluation of each cut-set order. (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. 299-308.
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
7234005
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ESSOR REACTOR; FAULT TREE ANALYSIS; IN PILE LOOPS; RELIABILITY
Descriptors DEC
ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; ORGANIC COOLED REACTORS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; RESEARCH AND TEST REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS

Optional Information

Secondary number(s)
IAEA-SM--195/46.