Hiroshi OKADA
著者に関連した記事は5件です。
更新情報
論文
保守管理 のためのリスク可視化手法の開発
著者:
小嶋 正義, Masayoshi KOJIMA , 高橋 秀治, Hideharu TAKAHASHI , 内田 俊介 , Shunsuke UCHIDA , 岡田 英俊, Hidetoshi OKADA , 木倉 宏成 , Hiroshige KIKURA
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キーワードタグ:
Failure Mode and Effect Analysis Maintenance Management Probabilistic Fracture Mechanics Risk Communication Visualization
小嶋 正義, Masayoshi KOJIMA , 高橋 秀治, Hideharu TAKAHASHI , 内田 俊介 , Shunsuke UCHIDA , 岡田 英俊, Hidetoshi OKADA , 木倉 宏成 , Hiroshige KIKURA
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Failure Mode and Effect Analysis Maintenance Management Probabilistic Fracture Mechanics Risk Communication Visualization
In order to improve safety of major equipments in nuclear power plants, an advanced FMEA (Failure Mode and Effect Analysis) was developed which was integrated PFM (probabilistic fracture mechanics) into the proven FMEA by evaluating the risk priority number in maintenance management based on a trio of anomaly occurrences in equipments (O), their severity (S) and their detectability (D). The results of equipement risk evaluation were visualized by evaluating the triangle area in the radar chart of three para...
英字タイトル:
Development of Visualization Method of Risk for Maintenance Management
英字タイトル:
Development of Visualization Method of Risk for Maintenance Management
第10回
原子力発電所の各種漏洩事象評価手法の高度化に関する研究
著者:
岡田 健志,Takeshi OKADA,奈良林 直,Tadashi NARABAYASHI,辻 雅司,Masashi TSUJI,千葉 豪,Go CHIBA,宮野 廣,Hiroshi MIYANO,松本 昌昭,Masaaki MATSUMOTO
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early detection infinitesimal leakage leak evaluation safety evaluation of systems SB-LOCA
岡田 健志,Takeshi OKADA,奈良林 直,Tadashi NARABAYASHI,辻 雅司,Masashi TSUJI,千葉 豪,Go CHIBA,宮野 廣,Hiroshi MIYANO,松本 昌昭,Masaaki MATSUMOTO
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early detection infinitesimal leakage leak evaluation safety evaluation of systems SB-LOCA
Various leak events have happened in nuclear power plants so far. And plants have bad conditions because of these leakages. Several leak events must be investigated, and we have to prepare these leakages. Like this, systematizing evaluation s of several leak events brings upgrades in regulations or new system of inspections, plans for aging deterioration. By using this method, we know deeper about Fukushima-Daiichi NPP. For example, here, from changes of CV pressure, we can conclude that SB-LOCA was NO...
英字タイトル:
Studies about Development of Leak Event Evaluation Method in Nuclear Power Plant
英字タイトル:
Studies about Development of Leak Event Evaluation Method in Nuclear Power Plant
解説記事
原子炉格納容器内部調査装置の開発および実証～形状変化形ロボット～
著者:
岡田 聡,Satoshi OKADA,石澤 幸治,Koji ISHIZAWA,高橋 良知,Yoshinori TAKAHASHI,遠藤 洋,Hiroshi ENDO
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岡田 聡,Satoshi OKADA,石澤 幸治,Koji ISHIZAWA,高橋 良知,Yoshinori TAKAHASHI,遠藤 洋,Hiroshi ENDO
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1. 概要 原子炉格納容器内部調査装置の 開発および実証 ~ 形状変化形ロボット ~ 日立 GE ニュークリア・エナジー(株) 岡田 聡 Satoshi OKADA 石澤 幸治 Koji ISHIZAWA 高橋 良知 Yoshinori TAKAHASHI 国際廃炉研究開発機構(IRID) 遠藤 洋 Hiroshi ENDO 福島第一原子力発電所の廃止措置に向け、 原子炉格 納容器 (PCV) 内部を調査するための装置を開発した [1] [2]。 PCV 内は放射線量が高く、 放射性物質飛散防止の観 点か......
第7回
敦賀発電所１号機の４０年目の高経年化技術評価の概要
著者:
津田 保,Tamotsu TSUDA,楠 丈弘,Takehiro KUSUNOKI,岡田 寛,Hiroshi OKADA,山田 多士,Takeshi YAMADA
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Ageing management technical evaluation (AMTE) JAPC PLM Tsuruga year
津田 保,Tamotsu TSUDA,楠 丈弘,Takehiro KUSUNOKI,岡田 寛,Hiroshi OKADA,山田 多士,Takeshi YAMADA
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Ageing management technical evaluation (AMTE) JAPC PLM Tsuruga year
Japan Atomic Power Company (JAPC) has completed the Ageing Management Technical Evaluation (AMTE) for Tsuruga Power Station unit 1 that has entered 40-year operation first in Japan, and has established the long-term maintenance management policy based on the evaluation. JAPC conducted the AMTE in accordance with “Ageing Management Implementation Guideline for Nuclear Power Plants“, “Code on Implementation and review of Nuclear Power Plant Ageing Management Programs 2008“ etc. During the 40-years AMTE, the ...
英字タイトル:
Overview of the technical evaluation of 40-year Plant Life ManagementTsuruga Power Station unit 1
英字タイトル:
Overview of the technical evaluation of 40-year Plant Life ManagementTsuruga Power Station unit 1
第11回
超高純度ステンレス鋼SUS310EHP の部材製作技術開発
著者:
岡田 聖貴,Kiyotaka OKADA,杉山 裕志,Hiroshi SUGIYAMA,蝦名 哲成,Tetsunari EBINA,加納 洋一,Yoichi KANO,中山 準平,Junpei NAKAYAMA,曽我 幸弘,Yukihiro SOGA
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Fabrication Technology Reprocessing Stainless Steel SUS310EHP Weldability
岡田 聖貴,Kiyotaka OKADA,杉山 裕志,Hiroshi SUGIYAMA,蝦名 哲成,Tetsunari EBINA,加納 洋一,Yoichi KANO,中山 準平,Junpei NAKAYAMA,曽我 幸弘,Yukihiro SOGA
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Fabrication Technology Reprocessing Stainless Steel SUS310EHP Weldability
The Extra High Purity Stainless Steel “SUS310EHP” has been developed to use in high oxidizing environments of the reprocessing plant. This stainless steel has higher intergranular-corrosion-resistance than R-SUS304ULC that is used in Rokkasho Reprocessing Plant. The SUS310EHP fabrication technology was verified by making sheets, plates and tubes. Moreover, the weldability of this stainless Steel was also investigated using the sheets, plates and tubes. ...
英字タイトル:
Development of Fabrication Technology of the Extra High Purity Stainless
英字タイトル:
Development of Fabrication Technology of the Extra High Purity Stainless