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.3 No.4 previous AA 37 - 38 - NT 44 - 45
Academic Articles
Regular Paper Vol.4No.1 (2012) p.22 - p.35
 

Capability of Ultrasonic Testing for Cast Austenitic Stainless Steel in Japanese Pressurized Water Reactors

 
Kazunobu SAKAMOTO1,*Takashi FURUKAWA2,Ichiro KOMURA2, Youitsu YAGIHASHI2 and Tsuyoshi MIHARA3
 
1Japan Nuclear Energy Safety Organization, 4-1-28, Toranomon, Minato-ku, Tokyo, 105-0001, Japan
2Japan Power Engineering and Inspection Corporation, 14-1, Benten-cho, Tsurumi-ku, Yokohama, 230-0044, Japan
3University of Toyama, 3190 Gofuku, Toyama-shi, Toyama, 930-8555, Japan.
 
Abstract
Flaw detection and sizing capabilities for cast austenitic stainless steel (CASS) which is widely used in primary loop of Japanese pressurized water reactors (PWR) are studied using conventional UT techniques currently applied on the CASS in in-service inspection program in Japan, Phased Array (PA) technique, as well as inspection by large size probe. The objective of the study was to make sure the accuracy of detection and sizing of inner surface flaws from the outside diameter piping surface by ultrasonic testing (UT) of which primary mode is longitudinal wave.
The result showed that currently available UT techniques are capable to detect the small cracks stable enough under postulated accident loads even after the thermal aging. With regard to the sizing capability, the result suggested that some consideration shall be taken into account when applying the technique if cracks were detected and technical breakthrough might be expected in the future.
 
Keywords
Cast austenitic stainless steel, CASS, Pressurized Water Reactor, PWR, Ultrasonic testing, UT
 
Full Paper: PDF EJAM Vol.4No.1 pp22.-35 "Capability of Ultrasonic Testing for Cast Austenitic Stainless Steel in Japanese Pressurized Water Reactorss
Article Information
Article history:
Received 26 Dec 2011
Accepted 22 May 2012