Published December 1984 | Version v1
Report Metadata-only

Containment loading during severe core damage accidents

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

The paper assesses the reactor containment loading during a severe accident sequence for a 900 MWe PWR unit. Calculations are performed by using the JERICHO thermalhydraulics code concerning the following cases: dry cavity with corium not cooled and flooded cavity with corium cooled. (orig.)

Additional details

Publishing Information

Imprint Title
5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 2
Imprint Pagination
664 p.
Journal Page Range
p. 1259-1271.
Report number
KFK--3880/2

Conference

Title
5. international meeting on thermal nuclear reactor safety.
Dates
9-13 Sep 1984.
Place
Karlsruhe (Germany, F.R.).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
16068503
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT; CORIUM; DRYOUT; EROSION; FISSION PRODUCT RELEASE; MELTDOWN; PWR TYPE REACTORS; REWETTING
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS