Determination of limits for smallest detectable and largest subcritical leakage cracks in piping systems
Creators
- 1. Siemens AG, Offenbach (Germany). Power Generation Group
- 2. Bayernwerk AG, Munich (Germany)
- 3. Rheinisch-Westfaelische Elektrizitaetswerke AG, Essen (Germany)
Description
Nuclear power plant piping systems - those still in their original as-built condition as well as upgraded designs - are subject to safety analysis. In order to limit the consequences of postulated piping failures, the basic safety concept incorporating rupture preclusion criteria is applied to specific high-energy piping systems. Leak-before-break analyses are also conducted within the framework of this concept. These analyses serve to determine the potential consequences of jet and reaction forces due to maximum subcritical leakage cracks while also establishing the minimum crack sizes that would be reliably detectable by the leakage rates resulting from these cracks. The boundary conditions for these analyses are not clearly defined. Using various examples as a basis, this paper presents and discusses how the leak-before-break concept can be applied. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 159
- Journal Issue
- 1
- Series
- Extended and updated selected papers from the 19th MPA seminar, Stuttgart, Germany, 7-8 October, 1993.
- Journal Page Range
- p. 29-42.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 27041776
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; CRACKS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; LEAK DETECTORS; NUCLEAR POWER PLANTS; PIPES; POWER SYSTEMS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RELIABILITY; RUPTURES; SAFETY ANALYSIS; STRESS ANALYSIS; STRESS INTENSITY FACTORS
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; MECHANICAL PROPERTIES; MECHANICS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS