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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
 
Abstract
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.
 
Keywords
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