Containment decompression-filtering system in French PWRs
Creators
- 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)
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.