Published September 1984
| Version v1
Journal article
The pressure course and the expansion of pressure waves in the case of sudden pipe failure
Creators
Description
For evaluating pipe systems in pressurized water reactors, investigations on pipes which showed axial partial breakages were carried out. The pressure relief process which starts with the pipe failure and was superimposed by pressure waves is described. The expansion of the pressure waves is compared with the results of a calculation model by Woollatt. Their effects on the course of failure are discussed. (orig.)
Abstract (German)
Zur Beurteilung von Rohrleitungssystemen in Druckwasserreaktoren wurden Untersuchungen an Rohren vorgenommen, die axiale Teildurchrisse aufwiesen. Der mit dem Rohrversagen einsetzende Druckentlastungsvorgang, der von Druckwellen ueberlagert wurde, wird beschrieben. Die Ausbreitung von Druckwellen wird mit Ergebnissen eines Berechnungsmodells von Woollatt verglichen. Ihre Auswirkungen auf den Versagensablauf werden eroertert. (orig.)Additional details
Additional titles
- Original title (German)
- Druckverlauf und Druckwellenausbreitung bei ploetzlichem Rohrversagen
Publishing Information
- Journal Title
- Brennst.-Waerme-Kraft
- Journal Volume
- 36
- Journal Issue
- 9
- Series
- CODEN: BRWKA.;Brennst.-Waerme-Kraft.
- Journal Page Range
- 377-384
- ISSN
- 0006-9612
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16039103
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DEFORMATION; FAILURES; LEAKS; PIPES; PRESSURE DEPENDENCE; PRESSURE MEASUREMENT; PRESSURE RELEASE; PWR TYPE REACTORS; RUPTURES; SHOCK WAVES; TIME DEPENDENCE; TUBES; VELOCITY; WAVE PROPAGATION
- Descriptors DEC
- ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS