Published 1990 | Version v1
Report Open

Early localization of containment leakage during an accident

Creators

  • 1. CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire
  • 2. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. d'Etudes Mecaniques et Thermiques

Description

In case of an accident in a nuclear plant, checking the containment leaktightness would be a fundamental step for the diagnosis and prognosis of the radiological consequences. Significant help in this task can be provided by softwares. For that purpose, the French Atomic Energy Commission (CEA) is developing an expert system which can provide early in the accident a classification of the possible leakage paths and help understanding the necessary corrections which have to be undertaken by the utility. This software will be used at the Emergency Technical Center of the CEA. Its basic principles are described in this paper

Availability note (English)

MF available from INIS under the Report Number.

Files

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Additional details

Publishing Information

Imprint Pagination
12 p.
Report number
CEA-DAS--740

Conference

Title
2. International conference on containment design and operation.
Dates
14-17 Oct 1990.
Place
Toronto, ON (Canada).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
22034868
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT BUILDINGS; EXPERT SYSTEMS; LEAKS; PWR TYPE REACTORS; REACTOR ACCIDENTS
Descriptors DEC
ACCIDENTS; BUILDINGS; CONTAINMENT; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS