ICMST-Tohoku 2018
Oct. 23 - 26, 2018
Sendai, Japan
ICMST-Shenzhen 2016
Nov 1 - 4, 2016
Shenzhen, China
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)

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

(in English)


Vol.11 No.2previousAA157- SP20 (AA158-159-160-161-162) NT94

Academic Articles
Regular Paper Vol.11 No.2 (2019) p.106 - p.111

Material research on RPV in decommissioning Hamaoka unit-1 (Progress report)


Hideki YUYA1,*, Masataka OYAMA1, Ryoya KOBAYASHI2, Kohey OTOMO2 and Akihiko KIMURA3

1 Nuclear safety R&D center, Chubu Electric Power, Co., Inc., 5561 Sakura, Omaezaki, Shizuoka 437-1695, Japan
2 Graduate School of Energy Science, Kyoto University, Yoshidahonmachi, Sakyou-ku, Kyoto 606-8501, Japan
3 Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011, Japan

Chubu electric power (Chubu) is now under investigation of radiation effects on the reactor pressure vessel (RPV) steel of a decommissioning BWR-4 in the Hamaoka unit-1 plant to confirm the validity of the current maintenance methodology and resultantly safety tolerance up to now. As a part of this program, we planned to survey the irradiation responses of the base metal just beneath the inner cladding of RPV. In this paper we report the results of Charpy impact and fracture toughness tests of a mock-up block of the archive material of RPV. The impact test using 1/3 sized specimens showed that the ductile brittle transition temperature (DBTT) of the base metal and cladding-HAZ (heat affected zone) were almost same, and the difference in the upper shelf energy (USE) between base metal and cladding-HAZ is within a scatter band. Fracture toughness test using compact tension (CT) specimens are successfully done and the results were compared with that in literature. Our data set of fracture toughness are considered to be consistent with a temperature dependent curve composed of past data.
FDecommissioning, Hamaoka, RPV, Harvesting, Irradiation embrittlement, cladding HAZ
Full Paper: PDF EJAM Vol. 11 No. 2 pp.106-111 "Material research on RPV in decommissioning Hamaoka unit-1 (Progress report) "
Article Information
Article history:
Received 11 November 2018
Accepted 11 September 2019