Published August 1994
| Version v1
Journal article
Load consequences of reactor pressure vessel failure at high primary system pressure
Creators
- 1. Inst. fuer Neutronenphysik und Reaktortechnik, Kernforschungszentrum Karlsruhe GmbH (Germany)
Description
The load acting on the pressure vessel of a PWR and its support girder after vessel failure at high primary system pressure (17 MPa) is estimated. The analysis is based on one-dimensional thermal-hydraulic calculations performed with the transient analysis code RELAP5/MOD3. The information obtained provides a force-function input for structural dynamic calculations of an increased containment for future nuclear power stations that can safely confine core-melt consequences. The computations lead to a maximum hydraulic load of 340 MN on the vessel support structure if a global circumferential rupture of the vessel lower head is assumed. (orig./HP)
Abstract (German)
Die auf den Reaktordruckbehaelter eines DWR und dessen Ringtraeger wirkenden Belastungen nach einem Versagen des Reaktordruckbehaelters bei hohem Primaersystemdruck (17 MPa) werden abgeschaetzt. Die Analyse basiert auf eindimensionalen thermohydraulischen Rechnungen mit dem Transientenanalyse-Programm RELAP5/MOD3. Die gewonnenen Informationen liefern Eingabedaten in Form von Last-Zeit-Funktionen fuer strukturdynamische Berechnungen eines verstaerkten Containments fuer zukuenftige Kernkraftwerke, das die Folgen eines Kernschmelzens sicher einschliessen kann. Die Rechnungen zeigen eine hydraulische Maximallast von 340 MN auf das Tragesystem des Behaelters unter der Annahme eines globalen Rundumabrisses des Behaelterbodens. (orig./HP)Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 59
- Journal Issue
- 4-5
- Journal Page Range
- p. 156-161.
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 25074162
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; CONTAINMENT; DYNAMIC LOADS; FAILURES; HIGH PRESSURE; ONE-DIMENSIONAL CALCULATIONS; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS