竹内 公人
著者に関連した記事は8件です。
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1.はじめに 東海第二発電所は,1978 年 11 月に運転を開始した電 気出力 110 万 kW の沸騰水型軽水炉(BWR-5)である。 東海第二発電所は定格熱出力一定運転中,東北地方太平 洋沖地震(茨城県東海村での観測震度「6 弱」)により, 平成23年3月11日 14時48分に「タービン軸受振動大(ト リップ設定値 0.25mm 以上)」による主発電機自動停止 (タービン主蒸気止め弁閉)の信号により原子炉が自動 停止した。この地震の影響により,「外部電源喪失」となっ たものの非常用ディーゼル発電機(......
第12回
我国の原子力発電所の運転期間40 年制限に関する 規制上の課題と提言
著者:
青木 孝行,Takayuki AOKI,竹内 公人,Kimihito TAKEUCHI,伊藤 邦雄,Kunio ITO,富田 洋一郎,Yoichiro TOMITA,高木 敏行,Toshiyuki TAKAGI
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Aging Management Back-fit Light Water Reactor Long Term Operation Plant Life Regulatory Limit
青木 孝行,Takayuki AOKI,竹内 公人,Kimihito TAKEUCHI,伊藤 邦雄,Kunio ITO,富田 洋一郎,Yoichiro TOMITA,高木 敏行,Toshiyuki TAKAGI
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Aging Management Back-fit Light Water Reactor Long Term Operation Plant Life Regulatory Limit
The nuclear reactor regulation law was amended three years ago (2012). In this amendment, the operation period of the commercial nuclear power plants in Japan was limited to 40 years. This limit may produce various problems in plant life management. So this paper proposes several recommendations for improvement. ...
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Recommendations related to the Problem of Limiting the Life of Japanese Nuclear Plants to 40 Years
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Recommendations related to the Problem of Limiting the Life of Japanese Nuclear Plants to 40 Years
第10回
改良型ＰＷＲ初号機設計への保全の知見・経験の反映
著者:
星野 知彦,Tomohiko HOSHINO,竹内 公人,Kimihito TAKEUCHI
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Advanced PWR Reflection of Operation and Maintenance Experience Tsuruga unit 3&4
星野 知彦,Tomohiko HOSHINO,竹内 公人,Kimihito TAKEUCHI
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Advanced PWR Reflection of Operation and Maintenance Experience Tsuruga unit 3&4
Tsuruga Unit 3&4 is the first APWR, which introduces a lot of improved technology aiming at safety, reliability and operability enhancement. This paper explains about our activities as to the reflection of our operation and maintenance experience including countermeasures against experienced troubles and plant life management evaluation result of operating PWRs in Japan. And the preparation for maintenance program introduction and basic policy for training of future operators and maintenance engineers...
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The Reflection of Operation and Maintenance Experience to the First Advanced PWR Design
英字タイトル:
The Reflection of Operation and Maintenance Experience to the First Advanced PWR Design
第7回
改良型ＰＷＲ初号機設計への保全の知見・経験の反映
著者:
星野 知彦,Tomohiko HOSHINO,竹内 公人,Kimihito TAKEUCHI
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Advanced PWR Reflection of Operation and Maintenance Experience Tsuruga unit 3&4
星野 知彦,Tomohiko HOSHINO,竹内 公人,Kimihito TAKEUCHI
発刊日:
公開日:
キーワードタグ:
Advanced PWR Reflection of Operation and Maintenance Experience Tsuruga unit 3&4
Tsuruga Unit 3&4 is the first APWR, which introduces a lot of impro ved technology aiming at safety, reliability and operability enhanc ement. This paper explains about our activities as to the reflecti on of our operation and maintenance experience including countermea sures against experienced troubles and plant life management evalua tion result of operating PWRs in Japan. And the preparation for mai ntenance program introduction and basic policy for training of fut ure operators and maintenance enginee...
英字タイトル:
The Reflection of Operation and Maintenance Experience to the FirstAdvanced PWR Design
英字タイトル:
The Reflection of Operation and Maintenance Experience to the FirstAdvanced PWR Design
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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Charpy impact test Reactor pressure vessel Surveillance test
中間 昌平,竹内 公人,林田 貴一,（日本原電）
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Charpy impact test Reactor pressure vessel Surveillance test
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.
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Report of the reactor pressure vessel steel material surveillance test results (the 4th) at Tokai No. 2 Power Station
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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Blowout panel E-Defense Severe accident
竹内 公人,林田 貴一,中間 昌平,（日本原電）
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Blowout panel E-Defense Severe accident
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....
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Development of reactor building blowout panel closing device for Tokai No.2 power station
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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ECT Extension of operation period MVT-1 Reactor pressure vessel Special inspection UT
中間 昌平,竹内 公人,林田 貴一,（日本原電）
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ECT Extension of operation period MVT-1 Reactor pressure vessel Special inspection UT
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
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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Aging management technical evaluation Neutron irradiation embrittlement SCC Thermal aging
中間 昌平,竹内 公人,林田 貴一,（日本原電）
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Aging management technical evaluation Neutron irradiation embrittlement SCC Thermal aging
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
英字タイトル:
Aging management technical evaluation for Tokai No.2 Power Station