Evaluation of material degradation of light water reactor structure using a miniaturized specimen sampled from actual components
- 1. Hitachi Ltd., Ibaraki (Japan). Mechanical Engineering Research Lab.
Description
The authors have proposed a miniaturized specimen method to evaluate the degree of sensitization for IASCC (irradiation assisted stress corrosion cracking), and fracture toughness using a small fragment sample from an actual component. This technique consists of two processes. The first process entails the sampling of a small fragment from the surface layer of the component by electric discharged machining (EDM). For this process a specially designed sampling electrode and technique have been developed. The results showed that the extraordinary layer was shallower than 300E m. This shallow extraordinary layer does not affect the evaluation of the material properties, because the surface layer of the sampled small fragment deeper than 300E m is removed when the test pieces are machined from the sampled fragment. The second process is a fracture toughness test using a miniaturized center cracked tension (CCT) specimen. The fracture toughness was evaluated by the stretch zone width (SZW) on the fracture surface. SZWs obtained in 1 mm thick CCT specimen well agreed with those in 1TCT specimen. However, SZW measured in 0.3 mm thick CCT specimen was about one fourth that of 1 TCT specimen, because SZW formation seems to be restricted by the deformation due to the plane stress condition on both sides of the CCT specimen. Accordingly, the macroscopic fracture toughness can be evaluated by measuring the SZW in a miniaturized CCT specimen with at least 1 mm thickness
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1226-X
- Imprint Title
- ICONE-4: Proceedings. Volume 5: Radioactive waste disposal; Decontamination and decommissioning; Aging assessment and license renewals; Global advances in nuclear codes and standards; Major component reliability
- Imprint Pagination
- 525 p.
- Journal Page Range
- p. 301-306.
Conference
- Title
- ASME/JSME international conference on nuclear engineering.
- Acronym
- ICONE 4
- Dates
- 10-13 Mar 1996.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27075577
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; EXPERIMENTAL DATA; FRACTURE PROPERTIES; MATERIALS TESTING; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; SAMPLE PREPARATION; STAINLESS STEEL-304; STRESS CORROSION
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; DATA; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NUMERICAL DATA; POWER REACTORS; RADIATION EFFECTS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TESTING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-960306--.