伊藤 肇
著者に関連した記事は5件です。
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保全の体系化について（第2回）―原子力発電所の保全技術― 伊藤 肇，宮口 仁一，田口 耕世，今野 隆博......
第3回
加圧水型原子力発電所におけるニッケル基合金使用部に関する保全技術について
著者:
伊藤 肇,Hajime ITO,平野 伸朗,Shinro HIRANO
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Alloy 600 Maintenance Nuclear power plant PWSCC Reactor vessel Steam generator
伊藤 肇,Hajime ITO,平野 伸朗,Shinro HIRANO
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Alloy 600 Maintenance Nuclear power plant PWSCC Reactor vessel Steam generator
Alloy 600, highly heat resistant and corrosion resistant, is widely used in nuclear power plant components, such as re actor pressure vessel nozzles and steam generator nozzles. However, some Alloy 600 components have recently experience d defects in Japan and abroad. In this regards, enhanced maintenance measures are required to deal with this problem. This paper describes representative defects; PWSCC in Alloy 600 components and summarizes countermeasures in advance....
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Maintenance Techniques on PWSCC of Ni Alloys Used as PWR Pressure Boundary Materials
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Maintenance Techniques on PWSCC of Ni Alloys Used as PWR Pressure Boundary Materials
規格基準動向1．はじめにAlloy600はPWR環境でSCC（以下PWSCC）の感受性があることから保全対策と関連規格の整備はPWR（加圧水型原子炉）の課題の一つとして認識されている。近年、Alloy600が使用されているPWR上蓋に海外で損傷事例が見られていたため、万一の場合の補修工法の確立は優先度の高い課題として検討されてきた。上蓋の補修にはき裂の存在する開先面に遠隔操作により３次元制御で健全な溶接を行う高度な技術を要する。さらに、規格についても、複雑形状のバウンダリ部におけるき裂進展評価、延性破壊評......
第2回
渦電流探傷法による環境遮断封止溶接部の疲労き裂検出及び残肉量推定について
著者:
遊佐 訓孝,Noritaka YUSA,ラディスラブ ヤノーセック,Ladislav JANOUSEK,ミハイ レビカン,Mihai REBICAN,陳 振茂,Zhenmao ZHEN,宮 健三,Kenzo MIYA,千種 直樹,伊藤 肇,Hajime ITO
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alloy 600 fatigue crack headpenetration non-destructive testing nuclear power plant weld overlay
遊佐 訓孝,Noritaka YUSA,ラディスラブ ヤノーセック,Ladislav JANOUSEK,ミハイ レビカン,Mihai REBICAN,陳 振茂,Zhenmao ZHEN,宮 健三,Kenzo MIYA,千種 直樹,伊藤 肇,Hajime ITO
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alloy 600 fatigue crack headpenetration non-destructive testing nuclear power plant weld overlay
Abstract: This study evaluates the applicability of eddy current testing to the detection and sizing of fatigue cracks embedded in Inconel weld overlay. Welded plate specimens, which model head penetration welds and their weld overlay, are fabricated, and fatigue cracks are artificially introduced into the specimens. Eddy current inspections are performed using a uniform eddy current probe driven with 10 kH z, and all of the fatigue cracks are detected with clear signals. Subsequent numerical inversions ...
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Detection of embedded fatigue cracks in weld overlay and evaluation of minimum thickness of the weld by means of eddy current testing
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Detection of embedded fatigue cracks in weld overlay and evaluation of minimum thickness of the weld by means of eddy current testing
第2回
美浜3号機二次系配管破損事故と今後の対応
著者:
伊藤 肇,Hajime ITO
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erosion / corrosion nuclear power plant secondary system
伊藤 肇,Hajime ITO
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erosion / corrosion nuclear power plant secondary system
Abstract: The secondary system pipe rupture occurred on August 9,2004, at Mihama nuclear power plant unit 3. Eleven workers, who were preparing for an annual outage that was to start from August 14th, suffered burn injuries, of who five died. We sincerely and deeply apologized to the victims and their families. We will make every possible effort to ensure that such an accident will never happen again. It is estimated that the disturbed flow of water, downstream of the orifice, caused erosion / corrosion an...
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Lesson learned from secondary pipe rupture at Mihama Unit 3 and our future strategy
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Lesson learned from secondary pipe rupture at Mihama Unit 3 and our future strategy