Akira KAI
著者に関連した記事は4件です。
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第9回
オーステナイトステンレス鋼における微小疲労き裂発生挙動と照)損傷の影響
著者:
中井 亮介,Ryosuke NAKAI,佐藤 佑毅,Yuki SATO,野上 修平,Shuhei NOGAMI,長谷川 晃,Akira HASEGAWA
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Fatigue Grain boundary Localized deformation Micro-crack Initiation Irradiation damage Proton irradiation Slip band Triple junction Twin boundary
中井 亮介,Ryosuke NAKAI,佐藤 佑毅,Yuki SATO,野上 修平,Shuhei NOGAMI,長谷川 晃,Akira HASEGAWA
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Fatigue Grain boundary Localized deformation Micro-crack Initiation Irradiation damage Proton irradiation Slip band Triple junction Twin boundary
The effect of irradiation on slip band formation and growth and micro-crack initiation behavior under low cycle fatigue in SUS316L austenitic stainless steel was investigated using accelerator-based proton irradiation and a low cycle fatigue test at room tem perature in air. The micro-crack initiation was observed at slip band, grain boundary, twin boundary, and triple junction regardless of the total strain range and the proton irradiation. In unirradiated specimens, the micro-crack initiation life droppe...
英字タイトル:
Fatigue Micro-crack Initiation Behavior and Effect of Irradiation Damage on Itin Austenitic Stainless Steel
英字タイトル:
Fatigue Micro-crack Initiation Behavior and Effect of Irradiation Damage on Itin Austenitic Stainless Steel
第10回
女川原子力発電所 主タービン設備における地震後の復旧工事について
著者:
河上 晃,Akira KAWAKAMI,渡辺 寛之,Hiroyuki WATANABE,齊藤 靖広,Yasuhiro SAITO,草階 達朗,Tatsuo KUSAKAI
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Bearing stand damage Earthquake Steam turbine Turbine blade
河上 晃,Akira KAWAKAMI,渡辺 寛之,Hiroyuki WATANABE,齊藤 靖広,Yasuhiro SAITO,草階 達朗,Tatsuo KUSAKAI
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Bearing stand damage Earthquake Steam turbine Turbine blade
The massive earthquake struck Onagawa nuclear power plant on March 11, 2011, and the nuclear reactor and the steam turbine was shut-down automatically. As a result of the post-earthquake steam turbine inspection, remarkable damages have been confirmed on the turbine blades and the bearing stands, and currently the restoration works have been conducted. This report introduces the damage status of the steam turbine caused by the earthquake, and activities of restoration work. ...
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Post-earthquake restoration work of the steam turbine at Onagawa Nuclear Power Plant
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Post-earthquake restoration work of the steam turbine at Onagawa Nuclear Power Plant
第3回
女川原子力発電所で発見された SCC 破面上の酸化皮膜評価
著者:
田附 匡,Tadashi TATSUKI,遠藤 利浩,Toshihiro ENDO,甲斐 彰,Akira KAI,庄子 哲雄,Tetsuo SHOJI
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Raman Spectroscopy Stainless Steel Stress Corrosion Cracking Surface Film TEM
田附 匡,Tadashi TATSUKI,遠藤 利浩,Toshihiro ENDO,甲斐 彰,Akira KAI,庄子 哲雄,Tetsuo SHOJI
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Raman Spectroscopy Stainless Steel Stress Corrosion Cracking Surface Film TEM
Characterization of oxide film on the SCC fracture surface was examined by using TEM and Micro Raman Spectrosc opy. The SCC sample cut from cracked component of the Onagawa Nuclear Power Plant was compared to CT-type labo ratory samples. The a-Fe2O3 distribution in the outer layer of the oxide film was the most characteristic of c rack growth rate. The enrichment of Cr was observed at crack tip and inner layer of all SCC samples with TEM....
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Evaluation of Oxide Film on the Surface of SCC at Onagawa Nuclear Power Plant
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Evaluation of Oxide Film on the Surface of SCC at Onagawa Nuclear Power Plant
第12回
高速炉プラント（「もんじゅ」）の安全性確保の考え方
著者:
岡田 俊親,Toshichika OKADA,市川 健太,Ichikawa KENTA,二神 敏,Futagami SATOSHI,江沼 康弘,Yasuhiro ENUMA,宮川 明,Akira MIYAKAWA,堺 公明,Takaaki SAKAI,中井 良大,Ryodai NAKAI
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Accident Management Fast Breeder Reactor Monju Safety Requirements Severe Accident
岡田 俊親,Toshichika OKADA,市川 健太,Ichikawa KENTA,二神 敏,Futagami SATOSHI,江沼 康弘,Yasuhiro ENUMA,宮川 明,Akira MIYAKAWA,堺 公明,Takaaki SAKAI,中井 良大,Ryodai NAKAI
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Accident Management Fast Breeder Reactor Monju Safety Requirements Severe Accident
Japan Atomic Energy Agency (JAEA) has organized “Pier Review Committee of Monju” consisting of experts on sodium cooled reactors and nuclear safety assessment in order to discuss and propose safety requirements for the prototype FBR Monju. JAEA is now researching the optimum plan in accordance with these safety requirements. Adopting another independent interlocking-system for the back-up shut-down system can reduce the accident risk of ULOHS: unprotected loss of heat sink. The heat transfer system of ...
英字タイトル:
Safety Requirements the Prototype Fast Breeder Reactor “Monju”
英字タイトル:
Safety Requirements the Prototype Fast Breeder Reactor “Monju”