江藤 淳二
著者に関連した記事は16件です。
更新情報
本稿においては、保全コストの低減と安全性向上の両立・最適化の実現に向けて、活用が期待されるデジタル技術に着目し、デジタル技術の導入事例等を紹介するとともに、一般的に指摘されているデジタル技術導入にあたっての課題、さらに原子力発電所の保全におけるAIの導入に向けたポイント等を解説する。...
第9回
米国高速炉廃材を用いた照射下ミクロ組織の非破壊検査技術開発(1) 実験的検討
著者:
匂坂 充行,Mitsuyuki SAGISAKA,江藤 淳二,Junji ETOH,松永 嵩,Takashi MATSUNAGA,枝川 文哉,Humiya EDAGAWA,礒部 仁博,Yoshihiro ISOBE,沖田 泰良,Taira OKITA
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キーワードタグ:
backscatter fast reactor irradiation damage microstructure non-destructive inspection structural material ultrasonic
匂坂 充行,Mitsuyuki SAGISAKA,江藤 淳二,Junji ETOH,松永 嵩,Takashi MATSUNAGA,枝川 文哉,Humiya EDAGAWA,礒部 仁博,Yoshihiro ISOBE,沖田 泰良,Taira OKITA
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backscatter fast reactor irradiation damage microstructure non-destructive inspection structural material ultrasonic
Development of methods of detecting degradation of irradiated reactor structural materials is required for successful operation of nuclear power plants. Ultrasonic waves, currently used as a non-destructive technique to detect cracks, change as a result of interacting with microstructural components and can be employed to measure radiation-induced changes in microstructure. Bulk-averaged measurements of microstructural changes can be determined usi ng ultrasonic velocity, attenuation and back-wall echo, wh...
英字タイトル:
Development of non-destructive inspection technique for microstructuresunder irradiation using decommissioned materials(1) An experimental approach
英字タイトル:
Development of non-destructive inspection technique for microstructuresunder irradiation using decommissioned materials(1) An experimental approach
第9回
米国高速炉廃材を用いた照射下ミクロ組織の非破壊検査技術開発(2)理論的検討
著者:
江藤 淳二,Junji ETOH,匂坂 充行,Mitsuyuki SAGISAKA,松永 嵩,Takashi MATSUNAGA,枝川 文哉,Humiya EDAGAWA,礒部 仁博,Yoshihiro ISOBE,沖田 泰良,Taira OKITA
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公開日:
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backscattering echo depth distribution microstructure stainless steel ultrasonic inspection void
江藤 淳二,Junji ETOH,匂坂 充行,Mitsuyuki SAGISAKA,松永 嵩,Takashi MATSUNAGA,枝川 文哉,Humiya EDAGAWA,礒部 仁博,Yoshihiro ISOBE,沖田 泰良,Taira OKITA
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backscattering echo depth distribution microstructure stainless steel ultrasonic inspection void
Abstract It is desired to develop an ultrasonic inspection technique non-destructively measuring various forms of irradiation-induced degradation in structural components of nuclear reactors. In order to evaluate the depth distributions of ir radiation-induced microstructural changes, we have developed a numerical simulation model of ultrasonic wave changes caused by microstructural changes in austenitic stainless steel based on the developed theory of ultrasonic wave propagation for comparison with experi...
英字タイトル:
Development of non-destructive inspection technique for microstructures under irradiation using decommissioned materials(2) An theoretical approach
英字タイトル:
Development of non-destructive inspection technique for microstructures under irradiation using decommissioned materials(2) An theoretical approach
第12回
超高純度ステンレス鋼(EHP 合金)の環境適用性評価
著者:
江藤 淳二,Junji ETOH,芦田 高規,Takaki ASHIDA,落合 孝正,Takamasa OCHIAI,木内 清,Kiyoshi KIUCHI,滝沢 真之,Masayuki TAKIZAWA,中山 準平,Junpei NAKAYAMA
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Austenitic stainless steel Corrosion Environmental assisted cracking Extra high purity
江藤 淳二,Junji ETOH,芦田 高規,Takaki ASHIDA,落合 孝正,Takamasa OCHIAI,木内 清,Kiyoshi KIUCHI,滝沢 真之,Masayuki TAKIZAWA,中山 準平,Junpei NAKAYAMA
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Austenitic stainless steel Corrosion Environmental assisted cracking Extra high purity
An elemental factor on the crack propagation mechanism of SCC observed in LWRs component materials made of non-sensitization stainless steels is examined with respect to the local steam corrosion in cracks by atomic oxygen formed at the wall surface under the irradiation of γray. The excellent oxidation resistance of type 25Cr-35Ni EHP steel with forming the protective double layer oxides is observed up to 600℃. On the other hand, the oxidation of type 316L steel with non-protective single oxide is acc...
英字タイトル:
Environmental compatibility evaluation of extra high purity stainless steel (EHP alloy)
英字タイトル:
Environmental compatibility evaluation of extra high purity stainless steel (EHP alloy)
第15回
軽水炉コンクリート構造物の照射劣化予測手法の開発に係る研究計画
著者:
滝沢 真之,鈴木 清照,江藤 淳二,河合 理城,藤山 翔乃,（三菱総研）,丸山 一平,（名古屋大）,紺谷 修,澤田 祥平,石川 俊介,（鹿島建設）
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Concrete FEM Irradiation LWR Neutron RBSM
滝沢 真之,鈴木 清照,江藤 淳二,河合 理城,藤山 翔乃,（三菱総研）,丸山 一平,（名古屋大）,紺谷 修,澤田 祥平,石川 俊介,（鹿島建設）
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Concrete FEM Irradiation LWR Neutron RBSM
A new research program of irradiation effects on LWR concrete member has been started since 2017. The previous research results indicate the reference level of neutron irradiation degradation on concrete should be set at 1 x 1019 n/cm2 which is one order of magnitude lower than the conventional reference level used in Japan. Several issues remain after the previous research and the objectives for clarifying the issues are set in the new project which is scheduled for five and half years. And international c...
英字タイトル:
The Research Plan on Development of Evaluation Method of LWR Concrete Irradiation Effect
英字タイトル:
The Research Plan on Development of Evaluation Method of LWR Concrete Irradiation Effect
第11回
逆止弁診断技術開発
著者:
松永 嵩,Takashi MATSUNAGA,江藤 淳二,Junji ETOH,稲川 聡,Satoshi INAGAWA,礒部 仁博,Yoshihiro ISOBE
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acoustic emission check valve condition based maintenance inspection ultrasonic testing
松永 嵩,Takashi MATSUNAGA,江藤 淳二,Junji ETOH,稲川 聡,Satoshi INAGAWA,礒部 仁博,Yoshihiro ISOBE
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acoustic emission check valve condition based maintenance inspection ultrasonic testing
We have developed Check Valve Inspection System using acoustic emission sensor and ultrasonic sensor, to examine degradation and detailed motion (Full open, Tapping, Oscillation, etc.) of the swing check valve. This inspection system was applied check valves in the seawater system line of domestic nuclear power plants. The examination was carried out before and after replacing the check valve. Comparing the results of the inspection system and the results of overhaul, effectiveness of this system has b...
英字タイトル:
Development of check valve inspection technique
英字タイトル:
Development of check valve inspection technique