Published 1986 | Version v1
Book

Containment decompression-filtering system in French PWRs

  • 1. Service Etudes et Projets Thermiques et Nucleaires, Electricite de France, Villeurbanne
  • 2. Electricite de France, 75 - Paris. Region d'Equipement

Description

As part of the plan to improve the safety of French PWRs, Electricite de France (EDF) has had to take additional steps to deal with situations beyond the design basis accident. The situations which are considered to be within the limit of a design basis accident are covered by what are called ''H'' procedures, which aim to prevent any risk of serious fuel degradation. These procedures have made it possible to reduce considerably the residual risk. Nevertheless, the authors study extreme case procedures intended to facilitate the implementation of emergency plans and to ensure better control of the containment of radioactive substances during highly improbable situations following major damage to the reactor core. In response to requests made by the French safety authorities, EDF has studied the possibility of installing an additional decompression-filtering device which was not planned at the design stage. The device selected makes use of a penetration already existing in the containment. It includes isolating valves and control elements designed for the situations envisaged, a filtering tank and removal of gases filtered at the common control point for gaseous effluent from the facility. Its installation, which is designed to facilitate the implementation of emergency plans and to limit any release of radioactive substances during serious accidents, therefore complements the traditional safety procedures in France. (author)

Part of:
Source term evaluation for accident conditions

Additional details

Additional titles

Original title (French)
Le systeme de decompression-filtration de l'enceinte de confinement des REP francais

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna (Austria)
ISBN
92-0-020086-9
Imprint Title
Source term evaluation for accident conditions
Imprint Pagination
777 p.
Series
Proceedings series.
Journal Page Range
p. 725-731.

Conference

Title
International symposium on source term evaluation for accident conditions.
Dates
28 Oct - 1 Nov 1985.
Place
Columbus, OH (USA).

INIS

Country of Publication
Austria
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
17062849
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT; DEPRESSURIZATION SYSTEMS; DESIGN BASIS ACCIDENTS; EMERGENCY PLANS; FILTERS; FISSION PRODUCT RELEASE; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; SPECIFICATIONS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs.
Secondary number(s)
IAEA-SM--281/37.