Published 2003 | Version v1
Computer medium

Program of in-pile IASCC testing under the simulated actual plant condition. Development of technique for in-pile IASCC growth test in JMTR

  • 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)

Part of:
ICONE-11: Proceedings of the 11th international conference on nuclear engineering

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)

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