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.9 No.2previous AASP17 (125-126-127-128-129-130-131-132-133-134-135-136-137-138-139-140-141-142) NT85
Academic Articles
Regular Paper Vol.9 No.2 (2017) p.72 - p.77
 

Evaluation of Hardening under Ion Irradiation in Reactor Pressure Vessel Model Alloys by Nano-indentation Techniques

 
Liang CHEN1,2, Kenji NISHIDA3, Kenta MURAKAMI4, Tomohiro KOBAYASHI2, Zhengcao LI5 and Naoto SEKIMURA1,*
 

1Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656, Japan
2Central Research Institute of Electric Power Industry, 2-11-1 Iwadokita, Komae-shi, Tokyo 201-8511, Japan
3Central Research Institute of Electric Power Industry, 2-6-1 Nagasaka, Yokosuka-shi, Kanagawa 240-0196, Japan
4Nuclear Professional School, School of Engineering, The University of Tokyo, 2-22 Shirakata, Tokai-mura, Ibaraki 319-1188, Japan
5School of Materials Science and Engineering, Tsinghua University, Beijing 100084, China

 
Abstract
The neutron irradiation embrittlement of reactor pressure vessel (RPV) steels needs to be properly predicted and managed for the safe long-term operation of light water reactors. To investigate the effects of the solute elements Ni, Mn and Si on the irradiation hardening at high dose levels, pertinent to long-term operation, in RPV materials without Cu, ion irradiation for Fe-1.0Ni-0.2Si, Fe-1.0Ni-1.4Mn and Fe-1.0Ni-1.4Mn-0.2Si alloys was carried out at 290 oC up to 5.0 dpa by Fe-ions with the energy of 2.8 MeV. Nano-indentation techniques were applied to evaluate the ion irradiation hardening. The results show that Mn significantly accelerates the irradiation hardening and addition of Si reduces the irradiation hardening. The depth dependence of irradiation hardening was discussed, and the irradiation hardening was the most significant at the indentation depth of about 120 nm in all alloys. The hardening behavior in deeper region was slightly different from that observed at about 120 nm depth, which may be caused by the interactions between solutes and defects.
 
Keywords
reactor pressure vessel, long-term operation, irradiation embrittlement, irradiation hardening, ion irradiation, nano-indentation
 
Full Paper: PDF
Article Information
Article history:
Received 12 October 2016
Accepted 29 May 2017