Takayuki SATO
著者に関連した記事は5件です。
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第8回
円管内オリフィス背後の物質輸送現象に関する研究 -シュミット数の影響-
著者:
佐藤 祐紀,Yuki SATO,山縣 貴幸,Takayuki YAMAGATA,伊藤 晃宏,Akihiro ITO,藤澤 延行,Nobuyuki FUJISAWA,高野 剛,Tsuyoshi TAKANO
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Flow accelerated corrosion Mass transfer Orifice Pipe wall thinning Schmidt number
佐藤 祐紀,Yuki SATO,山縣 貴幸,Takayuki YAMAGATA,伊藤 晃宏,Akihiro ITO,藤澤 延行,Nobuyuki FUJISAWA,高野 剛,Tsuyoshi TAKANO
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Flow accelerated corrosion Mass transfer Orifice Pipe wall thinning Schmidt number
In this paper, experimental and numerical studies are carried out to understand the pipe-wall thinning caused by the flow accelerated corrosion behind an orifice in a circular pipe. The measurement of mass transfer coefficient is carrie d out using a wall material of benzoic acid in a water flow, which allows the measurement of mass transfer behind the orifice in a circular pipe at Schmidt number 300 and 700, which is comparatively close to the actual condition in the prototype pipeline of nuclear power pl...
英字タイトル:
Study on Mass Transfer Phenomenon behind an Orifice in a Circular Pipe - Effect of Schmidt Number -
英字タイトル:
Study on Mass Transfer Phenomenon behind an Orifice in a Circular Pipe - Effect of Schmidt Number -
第1回
東海第二発電所 リスク評価手法の運転保守合理化への活用可能性について
著者:
森 智美,Tomomi MORI,江村 和伸,Takanobu EMURA,出雲 孝,Takashi IZUMO,青木 孝行,Takayuki AOKI,山中 勝,Masaru YAMANAKA,福山 智,Satoru FUKUYAMA
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Failure Probability PSA Risk-Informed Importance SSC
森 智美,Tomomi MORI,江村 和伸,Takanobu EMURA,出雲 孝,Takashi IZUMO,青木 孝行,Takayuki AOKI,山中 勝,Masaru YAMANAKA,福山 智,Satoru FUKUYAMA
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Failure Probability PSA Risk-Informed Importance SSC
Abstract This study proposes the risk-informed classification of structures, systems, and components (SSCs) and the possibility of applying risk-informed evaluation for operation and maintenance improvement. The resul ts of the risk importance ranking of SSCs are potentially formed into engineering databases to rationalize m anagement processes of the plant operation/maintenance by appropriate re-distribution of available resources....
英字タイトル:
Study on the Possibility of Applying Risk-Informed Evaluation for Operation and Maintenance Improvement at Tokai-2
英字タイトル:
Study on the Possibility of Applying Risk-Informed Evaluation for Operation and Maintenance Improvement at Tokai-2
第6回
高温水中におけるオーステナイト系合金の高応力下酸化-2 表面硬化層の影響評価
著者:
竹田 陽一,Yoichi TAKEDA,佐藤 崇之,Takayuki SATO,庄子 哲雄,Tetsuo SHOJI,大地 昭生,Akio OHJI
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Boiling Water Reactor Oxide Film Stainless Steel Stress Corrosion Cracking
竹田 陽一,Yoichi TAKEDA,佐藤 崇之,Takayuki SATO,庄子 哲雄,Tetsuo SHOJI,大地 昭生,Akio OHJI
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Boiling Water Reactor Oxide Film Stainless Steel Stress Corrosion Cracking
Surface oxide behavior on alloys in high temperature plays an important role in the stress corrosion clacking (SCC) mechanism according to plausibl e existing SCC models. In this investigation, roughness analysis of oxide/alloy interface on stainless steels after exposure in oxygenated high pur ity water under high stress conditions. A special emphasis was placed on how the oxidation penetration localized and went through the surface harde ned layer. It was pronounced that SCC initiation on hardened layer ...
英字タイトル:
Oxidation Behavior of Austenitic Alloys under High Stress Condition in High Temperature Water-Effect of Surface Hardened Layer
英字タイトル:
Oxidation Behavior of Austenitic Alloys under High Stress Condition in High Temperature Water-Effect of Surface Hardened Layer
第6回
高温水中におけるオーステナイト系合金の高応力下酸化ｰ1・Cr 含有量の影響評価
著者:
佐藤 崇之,Takayuki SATO,竹田 陽一,Yoichi TAKEDA,庄子 哲雄,Tetsuo SHOJI,大地 昭生,Akio OHJI
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Boiling Water Reactor Ni-Base Alloy Oxide Film Stress Corrosion Cracking
佐藤 崇之,Takayuki SATO,竹田 陽一,Yoichi TAKEDA,庄子 哲雄,Tetsuo SHOJI,大地 昭生,Akio OHJI
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Boiling Water Reactor Ni-Base Alloy Oxide Film Stress Corrosion Cracking
In this study, nickel-chromium binary alloys are used on the oxidation test in high temperature water to reveal the effect of chromium conten t on the oxidation behavior under high stress condition. It was shown that the oxidation behavior was affected by chromium content, stress co ndition and surface hardened layer. The feature which induced the localization of oxidation behavior was found on the oxide film of low chro mium alloys. It was thought that the presence of threshold conditions about chromium c...
英字タイトル:
The Oxidation Behavior of Austenitic Alloys under High Stress Condition in High Temperature Water-Effect of Chromium Content
英字タイトル:
The Oxidation Behavior of Austenitic Alloys under High Stress Condition in High Temperature Water-Effect of Chromium Content
第11回
高速増殖原型炉「もんじゅ」の保全の在り方 ‐「もんじゅ」保全の特徴と軽水炉保全経験の反映‐
著者:
仲井 悟,Satoru NAKAI,西尾 竜一,Ryuichi NOSHIO,内橋 昌也,Masaya UCHIHASHI,金子 義久,Yoshihisa KANEKO,山下 裕宣,Hironobu YAMASHITA,青木 孝行,Takayuki AOKI
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FBR LWR O&M experiences Maintenance Monju Sodium
仲井 悟,Satoru NAKAI,西尾 竜一,Ryuichi NOSHIO,内橋 昌也,Masaya UCHIHASHI,金子 義久,Yoshihisa KANEKO,山下 裕宣,Hironobu YAMASHITA,青木 孝行,Takayuki AOKI
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FBR LWR O&M experiences Maintenance Monju Sodium
A sodium cooled fast breeder reactor (FBR) has unique systems and components and different degradation mechanism from light water reactor (LWR) so that need to establish maintenance technology in accordance with its features. The examination of the FBR maintenance technology is carried out in the special committee for considering the maintenance for Monju established in the Japan Society of Maintenology (JSM). As a result of the study such as extraction of Monju maintenance feature, maintenance technol...
英字タイトル:
Principles of MONJU Maintenance - Characteristic of MONJU maintenance and reflection of LWR maintenance experience to FBR-
英字タイトル:
Principles of MONJU Maintenance - Characteristic of MONJU maintenance and reflection of LWR maintenance experience to FBR-