Development of short crack nucleation and growth model for stainless steel based on experimental data
- 1. Institute of Nuclear Safety System Inc., Seika, Kyoto (Japan)
Description
Environmentally assisted cracking (EAC), which is represented by stress corrosion cracking or corrosion fatigue, is one of the most important subjects in the study of material degradation of light water reactors. A significant proportion of the lifetime of a component subject to EAC may be spent in crack initiation and subsequent growth and/or coalescence to produce cracks which can be evaluated by conventional linear elastic fracture mechanics approaches. In this study, the state of nucleation and growth of a short crack was investigated experimentally in the EAC of austenitic stainless steel(SUS304) at high-temperature primary water in PWR, and the number of cracks as a function of time and short crack growth rates was obtained. Based on the experimental data, a Monte Carlo model for crack nucleation, short crack interaction, coalescence and crack growth was formulated. (author)
Additional details
Publishing Information
- Journal Title
- INSS Journal
- Journal Issue
- no.6
- Journal Page Range
- p. 113-120
- ISSN
- 1340-4482
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31009132
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; FRACTURE MECHANICS; FRACTURE PROPERTIES; GRAIN BOUNDARIES; GRAIN GROWTH; MONTE CARLO METHOD; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; SIMULATION; STAINLESS STEEL-304; STRESS CORROSION
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CALCULATION METHODS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; MECHANICS; MICROSTRUCTURE; NICKEL ALLOYS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS