Published May 2004
| Version v1
Journal article
Implementation of measures for managing severe accidents in 3rd generation facilities as explained by the EPR example
Description
Accidents in reactors exceeding the design basis have been investigated in a variety of ways over the past thirty years and taken into account accordingly in the safety concepts of plants. The EPR is used as a model for describing the most important measures taken to manage severe accidents. The main analytical and experimental demonstrations backing the required functions have been completed for the measures developed for the EPR. The licensing procedures to be carried out within the framework of current and/or future construction projects will show the licensability of these measures. (orig.)
Abstract (German)
Auslegungsueberschreitende Stoerfaelle in Reaktoren wurden im Laufe der letzten 30 Jahre in unterschiedlicher Weise betrachtet und demenstprechend im Sicherheitskonzept der Anlagen beruecksichtigt. Am Beispiel des EPR werden die wesentlichen Massnahmen zur Beherrschung schwerer Stoerfaelle dargestellt. Fuer die fuer den EPR entwickelten Massnahmen sind die wesentlichen analytischen und experimentellen Nachweise zur Absicherung der Funktionen erbracht. Die im Rahmen aktueller bzw. zukuenftiger Bauprojekte durchgefuehrten Genehmigungsverfahren werden die Genehmigungsfaehigkeit dieser Massnahmen zeigen. (orig.)Additional details
Additional titles
- Original title (German)
- Implementierung von Massnahmen zur Beherrschung schwerer Stoerfaelle in Anlagen der 3. Generation am Beispiel EPR
Publishing Information
- Journal Title
- Atw. Internationale Zeitschrift fuer Kernenergie
- Journal Volume
- 49
- Journal Issue
- 5
- Journal Page Range
- p. 324-328
- ISSN
- 1431-5254
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 35072834
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; CONTAINMENT; CORE CATCHERS; FLASHING; MELTDOWN; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; SAFETY ENGINEERING; SIMULATION
- Descriptors DEC
- ACCIDENTS; ENGINEERING; ENRICHED URANIUM REACTORS; EVAPORATION; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS