Published 1982
| Version v1
Miscellaneous
Containment response and load during blowdown experiments
Description
In the blowdown tests V29.2 and V62.2 studied here after the reaction of the containment to sudden pressure release and the developing temperature differences were analyzed by means of the extension measurements on the containment steel shell carried out by the MPA-Stuttgart. The resulting strains allow the safety of the steel shell to failure during blowdown to be evaluated quantitatively. In order to determine the differences between a blowdown of the live steach line (discharge of steam) and the feedwater line (discharge of water and steam) to the load of the containment steel shell, the results of both tests are compared with one another. (orig.)
Availability note (English)
Available from Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.).Abstract (German)
Bei den nachstehend betrachteten Blowdown-Versuchen V 29.2 und V 62.2 sollte mit Hilfe der von der MPA-Stuttgart durchgefuehrten Dehnungsmessungen an der Containment-Stahlschale die Reaktion des Containments auf den ploetzlich freiwerdenden Druck sowie die sich dabei aufbauenden Temperaturdifferenzen analysiert werden. Die sich daraus ergebenden Beanspruchungen lassen die Sicherheit der Stahlschale gegen Versagen bei Blowdown quantitativ beurteilen. Um die Unterschiede zwischen einem Blowdown der Frischdampfleitung (Ausstroemung von Dampf) und der Speisewasserleitung (Ausstroemung von Wasser und Dampf) auf die Belastung der Containment-Stahlschale feststellen zu koennen, werden die Ergebnisse beider Versuche miteinander verglichen. (orig.)Additional details
Additional titles
- Original title (German)
- Reaktion und Beanspruchung des Reaktorsicherheitsbehaelters bei Blowdown-Versuchen
Publishing Information
- Imprint Title
- 6. status report of the HDR safety programme project of Karlsruhe Nuclear Research Centre, December 2, 1982
- Imprint Pagination
- 472 p.
- Journal Page Range
- p. 287-323.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 14776872
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BLOWDOWN; CONTAINMENT; CYLINDRICAL CONFIGURATION; FEEDWATER; HDR REACTOR; MECHANICAL VIBRATIONS; PIPELINES; PRESSURE DEPENDENCE; PRESSURE RELEASE; PRESSURE VESSELS; RUPTURES; STRAINS; TEMPERATURE DEPENDENCE; TIME DEPENDENCE; TWO-PHASE FLOW
- Descriptors DEC
- BWR TYPE REACTORS; CONFIGURATION; CONTAINERS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FAILURES; FLUID FLOW; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:6. Statusbericht des Projektes HDR-Sicherheitsprogramm des Kernforschungszentrums Karlsruhe, 2. Dezember 1982, Schule fuer Kerntechnik.;PHDR-Arbeitsbericht 05.12/82.