第17回
女性の現場進出を助ける取り組み~カプラ接続治具~
著者:
植村 真紀,木村 昭仁,齊藤 明博,家口 英克,(六ヶ所エンジニアリング),山本 好郎,外﨑 雅貴,(日本原燃)
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近年、保全現場への女性進出が増加しているが、女性に限らず体格や筋力の差異によっては作業が困難な場合もあり、作業の進捗を遅らせることも見受けられる。そこで本研究では、体格や筋力の差異を補うため の治具を考案し、これまで困難であった作業を可能にするとともに、身体的負荷の軽減・作業時間の平準化 を実現することでダイバーシティおよびインクルージョンへの道を拓くことを目的とする。...
第13回
廃止措置研究・人材育成等強化プログラムにおける人材育成活動
著者:
山崎 宰春,Saishun YAMAZAKI,小原 徹,Toru OBARA,矢野 豊彦,Toyohiko YANO,竹下 健二,Kenji TAKESHITA,加藤 之貴,Yukitaka KATO,赤塚 洋,Hiroshi AKATSUKA,木倉 宏成,Hiroshige KIKURA,塚原 剛彦,Takehiko TSUKAHARA,吉田 克己,Katsumi YOSHIDA,遠藤 玄,Gen ENDO,鷹尾 康一朗,Koichiro TAKAO,原田 雅幸,Masayuki HARADA,佐藤 勇,Isamu SATO,岩附 信行,Nobuyuki IWATSUKI,鈴森 康一,Koichi SUZUMORI,浅沼 徳子,Noriko ASANUMA,新井 剛,Tsuyoshi ARAI,川嶋 健嗣,Kenji KAWASHIMA,高木 直行,Naoyuki TAKAKI
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The research and education program “Advanced Research and Education Program for Nuclear Decommissioning (ARED)” is proceeded in Tokyo Tech with views to sustainable development of human resources having advanced knowledge and experiences concerning decommissioning engineering, and development of advanced technologies to resolve a number of complicated challenges. This paper reports about the present status of the development of human resources. ...
英字タイトル:
Human resource development for the research and education program in Tokyo Tech
第16回
東海第二発電所 原子炉圧力容器鋼材監視試験結果(第4回)の報告
著者:
中間 昌平,竹内 公人,林田 貴一,(日本原電)
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At Tokai No. 2 Power Plant, the fourth monitoring test is conducted to confirm the tendency of reactor pressure vessel steels to become brittle due to neutron irradiation. From the results of the Charpy impact test, the amount of transition of the upper shelf absorbed energy and the related temperature was evaluated, and it was confirmed that there was no significant tendency to embrittlement. We report the results of the 4th monitoring test and discuss the results. ...
英字タイトル:
Report of the reactor pressure vessel steel material surveillance test results (the 4th) at Tokai No. 2 Power Station
第16回
東海第二発電所 原子炉建屋ブローアウトパネル閉止装置の開発
著者:
竹内 公人,林田 貴一,中間 昌平,(日本原電)
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It has been newly required as a regulatory standard that the blowout panel installed in the reactor building of BWR can be closed promptly when it is opened. In Tokai No. 2 Power Plant, a blowout panel closing device was developed to meet this requirement. In this report, we describe the design of blowout panel closing device and report the result of vibration test conducted in E-Defense....
英字タイトル:
Development of reactor building blowout panel closing device for Tokai No.2 power station
第16回
東海第二発電所 運転期間延長に係わる原子炉圧力容器の検査
著者:
中間 昌平,竹内 公人,林田 貴一,(日本原電)
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At Tokai No. 2 Power Station, a special inspection is conducted in line with the application for approval of extension of operating period. In particular, for reactor pressure vessels, ultrasonic flaw inspection is performed on the base metal part of the trunk which has not been inspected during the conventional in-service inspection. For water supply nozzles, we are conducting eddy current flaw detection inspection for low alloy steel, which is the first in Japan. As a result of these inspections, no defec...
英字タイトル:
Reactor pressure vessel inspection for extension of operation period at Tokai No. 2 power station
第16回
東海第二発電所 高経年化技術評価(40年目)の概要
著者:
中間 昌平,竹内 公人,林田 貴一,(日本原電)
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Tokai No.2 Power Station (Tokai II) has been operated more than 40-years. At 2018,we completed the 40-years Aging Management Technical Evaluation (AMTE), and concluded that most of component and structure would be maintained their integrity by continued existing preservation activities, even assuming the operation period of 60 years. In this paper, we explain several technical matters that were particularly discussed at AMTE, for example, thermal aging for casting stainless steel, neutron irradiation embrit...
英字タイトル:
Aging management technical evaluation for Tokai No.2 Power Station
第17回
核燃料施設等の重要度評価手法の検討状況について
著者:
衣旗 広志,小玉 貴司,大柿 一史,(日本原燃)
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Under the new inspection system for nuclear facilities introduced in April 2020, SDP (Significance Determination Process) is applied to an inspection finding to determine its safety significance. Regarding nuclear fuel facilities, the features of them are hardly incorporated into the current evaluation method of SDP, because the evaluation method was basically developed for nuclear power plant. In order to solve this challenge, we are developing evaluation method of SDP for nuclear fuel facilities....
英字タイトル:
Progress report of evaluation method of SDP for Nuclear Fuel Facilities
第5回
歪みセンサへの応用を目指した金属ナノクラスタを分散した非晶質炭素膜
著者:
竹野 貴法,Takanori TAKENO,菅原 敏文,Toshifumi SUGAWARA,三木 寛之,Hiroyuki MIKI
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In this study, a novel strain sensor using metal-containing diamond-like carbon films is proposed. A film of several hundred nanometer in thickness was deposited onto silicon wafer. The strain sensitivi ty was measured by the 4-point bending test. The temperature coefficient of resistance was also calculated from the resuslts of temperature dependence of the resistance. The obtained results show that t he variation of normalized resistance has the relation against the applied strain and gauge factor was ca...
英字タイトル:
Nano-cluster dispersed amorphous carbon film for strain sensor applications
第8回
水中レーザ溶接装置の開発
著者:
徳永 泰明,Yasuaki TOKUNAGA,千田 格,Itaru CHIDA,椎原 克典,Katsunori SHIIHARA,田村 雅貴,Masataka TAMURA,福田 健,Takeshi FUKUDA,前原 剛,Takeshi MAEHARA,依田 正樹,Masaki YODA
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Toshiba has developed various laser-based maintenance and repair technologies and already applied to nuclear power plants. Laser beam welding technology has been developed as an SCC cou ntermeasure for aged components in PWRs and BWRs. This technology can also be used underwater by blowing shielding gas for creating a local dry area. This welding equipment has damage d etecting function of optical elements such as windows and optical fiber cables, and the laser beam spot position and diameter can be adjust...
英字タイトル:
Development of Underwater Laser Beam Welding Equipment
第9回
沿岸立地構造物塩害評価及び対策
著者:
滝下 貴行,Takayuki TAKISHITA,中安 文男,Fumio NAKAYASU,来馬 克己,Katsumi KURUBA,梅原 敏弘,Toshihiro UMEHARA,野村 満幸,Mitsuyuki NOMURA,山本 裕之,Hiroyuki YAMAMOTO
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Nuclear spent fuel intermediate storage facility is planned to be located in the Sea of Japan coast area. Therefore, there is risk of structure corrosion by sea salt aerosol. This study is the co rrosion risk evaluation and it's countermeasure of that facility....
英字タイトル:
Evaluation of Salt Damage Structure Located in the Coastal