Fracture mechanics evaluation for the cast duplex stainless steel after thermal aging
Description
For the primary coolant piping of PWRs in Japan, cast duplex stainless steel which is excellent in terms of strength, corrosion resistance, and weldability has conventionally been used. The cast duplex stainless steel contains the ferrite phase in the austenite matrix and thermal aging after long term service is known to change its material characteristics. It is considered appropriate to apply the methodology of elastic plastic fracture mechanics for an evaluation of the integrity of the primary coolant piping after thermal aging. Therefore, we evaluated the integrity of the primary coolant piping for an initial PWR plant in Japan by means of elastic plastic fracture mechanics. The evaluation results show that the crack will not grow into an unstable fracture and the integrity of the piping will be secured, even when such through wall crack length is assumed to equal the fatigue crack growth length for a service period of up to 60 years. (author)
Additional details
Publishing Information
- Publisher
- The Japan Welding Engineering Society
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- 2nd international workshop on the integrity of nuclear components
- Imprint Pagination
- 289 p.
- Journal Page Range
- p. 167-178
Conference
- Title
- 2. international workshop on the integrity of nuclear components
- Dates
- 20-21 Apr 1998
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 30030180
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; CRACKS; EVALUATION; FRACTURE MECHANICS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STAINLESS STEELS; TEMPERATURE RANGE 0400-1000 K; THERMAL DEGRADATION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS