Program of in-pile IASCC testing under the simulated actual plant condition. Development of technique for in-pile IASCC growth test in JMTR
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
- 2. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
- 3. Japan Atomic Power Co., Tokyo (Japan)
Description
The irradiation assisted stress corrosion cracking (IASCC) is one of the major concerns on the integrity of in-core materials not only for the light water reactors (LWRs) but also for the materials to be cooled by water in fusion reactor. Since the synergies of radiation and stress/water can not be reproduced outside reactor core, the in-pile IASCC testing is one of the key experiments to understand IASCC behavior. A high temperature water loop facility was, therefore, installed at the Japan Materials Testing Reactor (JMTR) to carry out the in-core testing. And research and development of several techniques for performing the in-pile IASCC testing have been conducted. This paper describes the current status of the development of several techniques for in-pile IASCC growth test in JMTR. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-11: Proceedings of the 11th international conference on nuclear engineering
- Imprint Pagination
- [3610 p.]
- Journal Page Range
- [5 p.]
Conference
- Title
- 11. international conference on nuclear engineering
- Acronym
- ICONE-11
- Dates
- 20-23 Apr 2003
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35045057
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; DYNAMIC LOADS; IN PILE LOOPS; IRRADIATION DEVICES; IRRADIATION PROCEDURES; JMTR REACTOR; PERFORMANCE TESTING; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; STRESS CORROSION; STRESSES
- Descriptors DEC
- CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Track No. 01, Session 1-6, ICONE-36119