Search


Information
ICMST-Tohoku 2018
Oct. 23 - 26, 2018
Sendai, Japan
ICMST-Shenzhen 2016
Nov 1 - 4, 2016
Shenzhen, China
(EXIT THIS PAGE)
ICMST-Kobe 2014
Nov 2(Sun) - 5(Wed), 2014
Kobe, Japan
Nuclear Regulation Authority Outline of the New Safety Standards for Light Water Reactors for Electric Power Generation
For Public Comment
Outline of New Safety Standard (Design Basis)
For Public Comment
New Safety Standards (SA) Outline (Draft)
For Public Comment
Outline of New Safety Standard(Earthquake and Tsunami)(DRAFT)
Issues
 

Vol.10 No.2(Aug)
Vol.10 No.1(May)
Vol.9 No.4(Feb)
Vol.9 No.3(Nov)

< Other Issues

 

Occasional Topics
OTjapan Measures for Tsunami Striking Nuclear Power Station in Japan
Special Article: The Great Tohoku Earthquake (1)
OTjapan The Tragedy of “To Be” Principle in the Japanese Nuclear Industry
EJAMOT_CN3_Figure1_The_outside_view_of_CEFR OTChinaPlanning and Consideration on SFR R&D Activities in China
< All Occasional Topics

Featured Articles
EJAM7-3NT72 A New Mechanical Condition-based Maintenance Technology Using Instrumented Indentation Technique
EJAM7-3NT73 Survey robots for Fukushima Daiichi Nuclear Power Plant

JSM
Contacts
(EJAM): ejam@jsm.or.jp
(JSM): secretariat@jsm.or.jp
HP: http://www.jsm.or.jp
(in English)

 

Vol.11 No.1previous AASP19(150-151-152-153-154-155)-AA156 NT93

Academic Articles
Regular Paper Vol.11 No.1 (2019) p.1 - p.7
 

Eddy Current Testing System for Heat Affected Zone of In-Core Monitor Housing Inner Surface

 

Noriyasu KOBAYASHI1,*, Fumikazu MORIKAWA2, Tomoki FUJITA3, Daisuke MATSUKAWA2, Takashi KASUYA2 and Kentaro TSUCHIHASHI3

 
1 Toshiba Energy Systems & Solutions Corporation, 8 Shinsugita-cho, Isogo-ku, Yokohama, Kanagawa 235-8523, Japan
2 Toshiba Energy Systems & Solutions Corporation, 2-4 Suehiro-cho, Tsurumi-ku, Yokohama, Kanagawa 230-0045, Japan
3 Toshiba Energy Systems & Solutions Corporation, 72-34 Horikawa-cho, Saiwai-ku, Kawasaki, Kanagawa 212-8585, Japan
 
Abstract
We verified that eddy current testing (ECT) has enough detectability for a welded part position of in-core monitor (ICM) housing outside and defects on a heat affected zone (HAZ) in welding of the inner surfaces for a special inspection involved in long-term operation. It is difficult to determine an appropriate inspection area if an actual welded position of an ICM housing is different from a designed position. It is presumed that detectability of ECT is decreased because a HAZ of an ICM housing inner surface is deformed by welding. We conducted a full-scale mock-up test using a simulated ICM housing specimen with a welded part and an ECT system which consisted of a welded part detection probe, a rotational ECT probe and probe moving equipment and confirmed that the ECT detected a welded part position of outside and defects of about 0.5 mm in depth despite existences of inner surface deformations of approximately 1 mm.
 
Keywords
Non-destructive inspection, Eddy current testing, Heat affected zone, In-core monitor housing, Nuclear reactor, Special inspection, Long-term operation
 
Full Paper: PDF EJAM Vol. 11 No. 1 pp.1-7 "Eddy Current Testing System for Heat Affected Zone of In-Core Monitor Housing Inner Surface"

Article Information
Article history:
Received 15 Oct. 2018
Accepted 24 May 2019