Published 1989
| Version v1
Journal article
The instability criterion for a circumferential through-wall crack in a bend in a stainless steel piping system: the effects of bend profile and bend angle
Description
Motivated by the problem of intergranular stress corrosion cracking of Type 304 stainless steel in Boiling Water Nuclear Reactor piping systems, the paper examines the stability of a circumferential through-wall crack in a bend in a piping system that is subjected to simulated accident loading conditions. The instability criterion is expressed in terms of the material tearing modulus TMAT and the applied tearing modulus TAPP (or the effective pipe length LEFF). The main thrust of the paper is the modelling of the bend profile and an assessment of the effect of bend angle on the instability criterion. (author)
Additional details
Publishing Information
- Journal Title
- International Journal of Pressure Vessels and Piping
- Journal Volume
- 40
- Journal Issue
- 2
- Series
- Int. J. Press. Vessels Piping.
- Journal Page Range
- 151-159
- ISSN
- 0308-0161
- CODEN
- PRVPA
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 21050092
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENDING; BWR TYPE REACTORS; CRACK PROPAGATION; MATHEMATICAL MODELS; PIPES; REACTOR COOLING SYSTEMS; STEEL-CR19NI10
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; DEFORMATION; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; NICKEL ALLOYS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; STAINLESS STEELS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS