Published December 1992 | Version v1
Journal article

Analysis of leak and break behavior in a failure assessment diagram for carbon steel pipes

  • 1. Mechanical Engineering Research Lab., Hitachi, Ibaraki (Japan)
  • 2. Hitachi Works, Ibaraki (Japan)

Description

The leak and break behavior of a cracked coolant pipe subjected to an internal pressure and a bending moment was analyzed with a failure assessment diagram using the R6 approach. This paper examines the conditions of the detectable coolant leakage without breakage. A leakage assessment curve, a locus of assessment point for detectable coolant leakage, was defined in the failure assessment diagram. The region between the leak assessment and failure assessment curves satisfies the condition of detectable leakage without breakage. In this region, a crack can be safely inspected by a coolant leak detector. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
138
Journal Issue
3
Journal Page Range
p. 251-258.
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Notes
Extended and updated paper from the 5th Japanese-German joint seminar, Munich (Germany), Oct 11-12, 1990.