Published 1989
| Version v1
Book
The instability of a circumferential through-wall crack in a bend in a stainless steel piping system
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 model piping system that is subject to fixed displacement loadings, that are appropriate for an accident condition. The instability criterion is expresses in terms of the material tearing modulus TMAT and the applied tearing modulus TAPP (or the equivalent pipe length LEFF), with particular attention being focussed on the effect of bend angle of LEFF
Additional details
Additional titles
- Subtitle (English)
- The effect of bend angle on the instability criterion
Publishing Information
- Publisher
- American Association for Structural Mechanics in Reactor Technology.
- Imprint Place
- Los Angeles, CA (USA)
- ISBN
- 0-9623306-0-4
- Imprint Title
- Transactions of the 10th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 375 p.
- Series
- Volume G. Fracture mechanics and non-destructive evaluation.
- Journal Page Range
- p. 353-356.
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21068164
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; DYNAMIC LOADS; INSTABILITY; INTERGRANULAR CORROSION; MATERIALS TESTING; PRESSURE VESSELS; REACTOR ACCIDENTS; REACTOR STABILITY; STEEL-CR19NI10
- Descriptors DEC
- ACCIDENTS; ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CONTAINERS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; NICKEL ALLOYS; POWER REACTORS; REACTORS; STABILITY; STAINLESS STEELS; STEELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890855--.