Thermal fatigue behavior of thin-walled cylindrical carbon steel specimens in simulated BWR environment
Description
Thin-walled cylindrical carbon steel specimens were thermally fatigued in a pressurized autoclave. Since high and low temperature pure water were alternately supplied into the autoclave, the specimens were subjected to homogeneous thermal stress through the wall thickness. The thermal fatigue life was defined as the number of cycles to crack penetration to the inside of the cylindrical specimen. The thermal fatigue strength was compared with the mechanical fatigue strength performed in air and in high temperature water. Even if taking account of the Higuchi-Iida formula, which considers the effects of strain rate, dissolved oxygen concentration and water temperature on fatigue life, the thermal fatigue lives of carbon steel were found to be slightly shorter than the mechanical fatigue lives. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 184
- Journal Issue
- 1
- Journal Page Range
- p. 123-133
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- PVP - exchanging international technology
- Acronym
- ASME/JSME pressure vessels and piping conference (PVP)
- Dates
- 23-27 Jul 1995
- Place
- Honolulu, HI (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 29051661
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CARBON STEELS; CRACK PROPAGATION; CYLINDERS; S-N DIAGRAM; STRAIN RATE; TEMPERATURE RANGE 0400-1000 K; THERMAL FATIGUE; THERMAL STRESSES; THICKNESS; WATER; WATER CHEMISTRY; YIELD STRENGTH
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMISTRY; DIAGRAMS; DIMENSIONS; ENRICHED URANIUM REACTORS; FATIGUE; HYDROGEN COMPOUNDS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; STEELS; STRESSES; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs.