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.12 No.1previousAA SP23 (AA172-173)-AA174 NT97
Academic Articles
Regular Paper Vol.12 No.1 (2020) p.14 - p.25
 

The effect of Dissolved Hydrogen for PWSCC Initiation test by Reverse U-Bend specimen of Alloy 600

 

Takaaki Kobayashi1 and Wataru Sugino2

 
1 Mitsubishi Heavy Industries, LTD, 1-1-1, Wadasaki-cho, Hyogo-ku, Kobe-city, Japan
1The Japan Atomic Power Campany, 5-2-1, Ueno, Taitou-ku, Tokyo, Japan
 
Abstract
In order to apply a more positive countermeasure against Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 600, an optimizing Dissolved Hydrogen (DH) concentration in primary water are expected in addition to a replacing to Alloy 690 or a stress improvement by water jet peening. PWSCC initiation test data depending on DH concentration are few. PWSCC initiation tests by Reverse U-Bend (RUB) specimens with the different pre-strain setting had been performed. PWSCC initiation test by 25% pre-strained RUB specimen also showed the same dependency on DH concentration as PWSCC crack growth test by CT specimen in also this study at 345°C as same as the previous study at 320°C by the authors. It’s considered due to the high stress applied to the material surface and the crevasse of oxide film on 25% pre-strained RUB specimen. On the other hand, the test by 10% pre-strained RUB specimen showed the different dependency on DH from the test by 25% pre-strained RUB specimen. It’s considered that the test by lower pre-strained RUB shows the result based on the protectable Cr enriched oxide film. The cold working rate to Alloy600 parts in the actual PWR is basically less than 10%. In order to correctly evaluate the susceptibility of PWSCC initiation depending on DH concentration for the actual PWR, it’s necessary to be performed PWSCC initiation test by a specimen applied a lower pre-strain or stress even if it need a long-term SCC test.
 
Keywords
Dissolved Hydrogen, Stress Corrosion Cracking, Nickel based alloy, Alloy 600, Nickel Oxide, PWSCC, Crack Initiation time, Crack Propagation Rate
 
Full Paper: PDF
Article Information
Article history:
Received 21 December 2019
Accepted 16 May 2020