第13回
軽水炉保全最適化のための統合型シミュレータ Dr. Mainte による ヒューマンエラーの影響とその低減効果の検討 2
著者:
礒部 仁博,Yoshihiro ISOBE,匂坂 充行,Mitsuyuki SAGISAKA,小川 良太,Ryota OGAWA,松永 嵩,Takashi MATSUNAGA,高坂 徹,Toru KOSAKA,松本 聡司,Satoshi MATSUMOTO,吉村 忍,Shinobu YOSHIMURA
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Dr. Mainte, an integrated simulator for maintenance optimization of LWRs (Light Water Reactors) has been developed based on PFM (Probabilistic Fracture Mechanics) analyses in terms of safety, availability and economic efficiency, environmental impact and social acceptance. For the further improvement of maintenance activities, the importance of reducing human errors is often pointed out. Human errors are well recognized to be affected by mental stress conditions. Due to the amendment of Industrial Safe...
英字タイトル:
Effects of Human Error and its Reduction Analyzed by Dr. Mainte, Integrated Simulator of Maintenance Optimization of LWRs 2
第12回
軽水炉保全最適化のための統合型シミュレータDr. Mainte による ヒューマンエラーの影響とその低減効果の検討
著者:
礒部 仁博,Yoshihiro ISOBE,匂坂 充行,Mitsuyuki SAGISAKA,小川 良太,Ryota OGAWA,松永 嵩,Takashi MATSUNAGA,高坂 徹,Toru KOUSAKA,松本 聡司,Satoshi MATSUMOTO,吉村 忍,Shinobu YOSHIMURA
発刊日:
公開日:
キーワードタグ:
Dr. Mainte, an integrated simulator for maintenance optimization of LWRs (Light Water Reactors) has been developed based on PFM (Probabilistic Fracture Mechanics) analyses. The concept of the simulator is to provide a decision-making system to optimize maintenance activities for representative components and piping systems in nuclear power plants totally and quantitatively in terms of safety, availability and economic efficiency, environmental impact and social acceptance. For the further improvement ...
英字タイトル:
Effects of Human Error and its Reduction Analyzed by Dr. Mainte, Integrated Simulator of Maintenance Optimization of LWRs
第13回
過酷事故対応のドライウェル冷却器の除熱特性
著者:
石田 直行,Naoyuki ISHIDA,綿引 直久,Naohisa WATAHIKI,細井 秀章,Hideaki HOSOI,渡邉 亮平,Ryohei WATANABE,佐藤 大樹,Daiki SATO
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日立 GE 安藤 浩二 Kouji ANDOU Non-Member The new dry-well cooler (DWC) for a severe accident has been developed to avoid release of radioactive materials to environment caused by primary containment vessel failure. The DWC can be operated using natural driving force to remove decay heat. The element tests using copper tube bundle with 3 rows and 5 levels were conducted under existing nuclear power plant conditions to estimate heat removal ratio with non-condensable gas (N2) and to confirm occurrence of natu...
英字タイトル:
Heat Removal Characteristics of Dry-well Cooler for a Severe Accident
論文
配管系の弾塑性解析手法の検討(その1)
著者:
小島 信之,Nobuyuki KOJIMA,蒲谷 拓郎,Takuro KABAYA,荒井 雅史,Masashi ARAI,廣内 悟,Satoru HIROUCHI,板東 雅嗣,Masatsugu BANDO
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This report describes an elasto-plastic analysis method which can be applied for the actual aseismic design of nuclear carbon steel piping systems. This analysis method follows the one developed by the related JSME tasks. Using this analysis method, the test result has been reproduced to the safe side for the strain range used as the intensity evaluation index of carbon steel piping. Furthermore, fatigue life has also been reproduced to the safe side by using the curve of fatigue of carbon steel piping upon...
英字タイトル:
Investigation on Method of Elasto-Plastic Analysis for Piping System (No.1)
第2回
電磁現象を用いた片状黒鉛鋳鉄の黒鉛形態の推定
著者:
野崎 俊彦,Toshihiko NOZAKI,佐藤 武志,Takeshi SATO,阿部 利彦,Toshihiko ABE,内一 哲哉,Tetsuya UCHIMOTO,高木 敏行,Toshiyuki TAKAGI
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This paper discusses the feasibility of characterization of graphite morphology in gray cast irons based on electromagnetic method. For the pur pose, gray cast iron with different graphite morphology was systematically evaluated. In order to discuss electromagnetic property of gray cast iron with different graphite morphology, conductivity and permeability were measured. It was found that both conductivity and permeability mai nly depend on graphite morphology. It was shown that the graphite morphology of ...
英字タイトル:
Characterization of graphite morphology of gray cast irons using electromagnetic method
第3回
電磁超音波・渦電流複合センサの開発とその有効性の検証
著者:
鈴木 研一郎,Kenichiro SUZUKI,内一 哲哉,Tetsuya UCHIMOTO,高木 敏行,Toshiyuki TAKAGI,佐藤 武志,Takeshi SATO,Philippe Guy,Amelie Casse
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In this study, we propose a novel EMAT-ECT multi sensor aiming at advanced structural health monitoring. For the purpose, proto-type EMAT-ECT multi-sensor was developed and their functions both as ECT and EMAT prove were evaluated. Experimental results of pulse ECT using the EMAT-ECT multi-sensor showed that the pr oposed sensor has a capability of detection and sizing of flaws. Experimental results of EMAT evaluation using the EMAT-ECT multi-sensor showed that ultrasoni c wave was transmitted by EMAT-ECT ...
英字タイトル:
Development of novel EMAT-ECT multi-sensor and verification of its feasibility
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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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
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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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
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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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-