An analysis of leak-before-break for nuclear piping with stress corrosion cracking
Creators
- 1. Univ. of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113
Description
Studies on structural safety of nuclear piping system in the presence of large flaws have been of much importance because of discoveries of stress corrosion crackings in several BWR plants. One important concept in consideration of structural integrity of piping with such a flaw is the so-called leak-before-break concept. The assessment of this concept requires understanding of fracture condition and development of estimation method. In this paper, studies on these problems are reviewed. First of all, a criterion of ductile crack growth is studied with the finite element analyses for plates and pipes. Next, crack growth behavior from a part-through crack is estimated using the criterion above. Finally, using the practical methods, leak-before-break condition is estimated for the actual piping
Additional details
Publishing Information
- Publisher
- International Assoc. for Structural Safety and Reliability.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Structural safety and reliability
- Journal Page Range
- p. III.233-III.242.
Conference
- Title
- 4. international conference on structural safety and reliability.
- Acronym
- ICOSSAR '85
- Dates
- 27-29 May 1985.
- Place
- Kobe (Japan).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18070077
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; CRACKS; DUCTILITY; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; LEAK TESTING; LEAKS; PIPES; POWER REACTORS; REACTOR SAFETY; RUPTURES; STAINLESS STEELS; STRESS CORROSION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; FAILURES; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MECHANICS; NUMERICAL SOLUTION; REACTORS; SAFETY; STEELS; TENSILE PROPERTIES; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS