第13回
福島第一原子力発電所使用済燃料プール貯蔵燃料及び燃料デブリ取出しに向けた取り組み
著者:
東倉 一郎,Ichiro TOKURA,篠崎 史人,Fumihito SHINOZAKI,鈴木 淳,Jun SUZUKI,浦西 敦義,Atsuyoshi URANISHI,大和 正樹,Masaki YAMATO,宮本 哲昌,Akimasa MIYAMOTO
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Toshiba and TEPCO completed the removal of large debris from the spent fuel pool (SFP) in November 2015. The large debris had been an obstacle to start the fuel debris removal work and had been necessary to be removed quickly in terms of risk reduction. Continuously, Toshiba and TEPCO are preparing for removal of small debris and spent fuels. Also, Toshiba and IRID are investigating of PCV interior and working in research and development to determine construction methods considering amount, location an...
英字タイトル:
Effort aimed at removal of stored fuels from SFP and fuel debris inside PCV in Fukushima Daiichi Nuclear Power Station
第12回
福島第一原子力発電所建屋内高所調査のためのロボット開発
著者:
山野辺 夏樹,Natsuki YAMANOBE,加藤 晋,Shin KATO,大山 英明,Eimei OYAMA,森川 泰,Yasushi MORIKAWA,横井 一仁,Kazuhito YOKOI
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Abstract: National Institute of Advanced Industrial Science and Technology (AIST) and Honda R&D Co., Ltd. (Honda) have developed a robot to survey high and complex areas in the reactor buildings at Fukushima Daiichi nuclear power station. The high-access survey robot consists of a high-area accessible crawler type work platform and a survey arm installed on top of the platform, both of which can be remotely controlled using an intuitive graphical user interface. The robot has been deployed three times ...
英字タイトル:
High-Access Survey Robot for Fukushima Daiichi Nuclear Power Station
第2回
結晶粒形状に注目した強度特性評価による材質制御・材料保全法の検討
著者:
原田 直樹,Naoki HARADA,勝山 仁哉,Jinya KATSUYAMA,樋口 良太,Ryota HIGUCHI,望月 正人,Masahito MOCHIZUKI,豊田 政男,Masao TOYODA
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This study proposes a numerical analysis method for evaluation of strength properties related with mater ial control and material maintenance. The method using generalized Voronoi diagram for modeling of hete rogeneity of grain shape is proposed. Effect of grain shape on strength properties is analyzed by the fi nite element method. ...
英字タイトル:
Investigation of Material Control and Material Maintenance Method by Evaluation of Strength Properties Considering Grain Shape
論文
表面加工による残留応力改善の長期信頼性評価について
著者:
瀬良 健彦,Takehiko SERA,平野 伸朗,Shinro HIRANO,千種 直樹,Naoki CHIGUSA,岡野 成威,Shigetaka OKANO,才田 一幸,Kazuyoshi SAIDA,望月 正人,Masahito MOCHIZUKI,西本 和俊,Kazutoshi NISHIMOTO
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Abstract Surface finishing methods, such as Water Jet Peening (WJP), have been applied to welds in some major components of nuclear power plants as a counter measure to Primary Water Stress Corrosion Cracking (PWSCC). In addition, the methods of surface finishing (buffing treatment) is being standardized, and thus the buffing treatment has been also recognized as the well-established method of improving stress. On the other hand, the long-term stability of peening techniques has been confirmed by acc...
英字タイトル:
Prediction method of long-term reliability in improving residual stresses by means of surface finishing
第10回
複雑形状部での物質伝達係数と形状係数
著者:
猪飼 太郎,Taro IKARI,片井 勇旭,Yuki KATAI,恒吉 達矢,Tatsuya TSUNEYOSHI,伊藤 高啓,Takahiro ITO,辻 義之,Yoshiyuki TSUJI
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Flow Accelerated Corrosion (FAC) is one of the issues to be noticed considerably in plant piping management. For the integrity and safety of t he plant, the wall-thinning and thinning rate due to FAC should be clely predicted in pipe wall inspection. In this paper, we study FAC fro m the view point of flow dynamics. The mass transfer coefficient is estimated by the numerical simulation inside the bent. Changing the Reynol ds number, the peak location of mass transfer coefficient and its maxim value is eval...
英字タイトル:
Mass Transfer and Shape Factor in Complicated Flow Field
解説記事
解説記事「海外における保守高度化の取組み」(2) 諸外国における 原子力発電所安全系設備に対する 運転中における保全活動の取組み
著者:
柘植 洋太 Yota TSUGE 伊藤 邦雄 Kunio ITO
発刊日:
公開日:
先行する米国、スペイン及びフィンランドにおけるOLMの実施状況や、背景、規制要件、規制・産業界ガイダンス、安全管理手法及びOLMの効果等について概説する。...
第13回
配管破損時の流体漏洩挙動に関する研究
著者:
渡辺 瞬,Shun WATANABE,米田 公俊,Kimitoshi YONEDA
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Domestic light water reactors are expected to restart sequentially after given permission in condition to meet the new regulatory requirements. Since several safety related systems were added to the plants through the process of the new regulatory requirements, the numbers of components to be inspected, which is already a large amount, will increase even more after the restart. Effective measure will be required to command maintenance activities by reasonably assigning limited resource. The authors hav...
英字タイトル:
Study on Fluid Leakage Behavior with Pipe Failure
第10回
配管要素の組み合わせにより発生した旋回流の 配管減肉に与える影響について
著者:
山本 啓,Kei YAMAMOTO,鈴木 翔太,Shota SUZUKI,中村 隆夫,Takao NAKAMURA,米田 公俊,Kimitoshi YONEDA,渡辺 瞬,Syun WATANABE
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Flow accelerated corrosion (FAC) is the major pipe wall thinning phenomena in power plants. The management of pipe wall thinning has been carried out to pipe elements such as elbow, orifice, etc. of the piping system in power plants. In piping system, it is known that several pipe elements which are connected in series may generate swirl flow. Therefore the arrangement of pipe elements is considered to affect thinning phenomena seriously. So the behavior of this swirl flow is one of the major research ...
英字タイトル:
EFFECT OF SWIRL FLOW GENERATED BY THE COMBINATION OF PIPE ELEMENTS ON WALL THINNING PHENOMENA
第9回
配管要素の組み合わせにより発生する旋回流の物質移動係数評価
著者:
鈴木 翔太,Shota SUZUKI,中村 隆夫,Takao NAKAMURA,米田 公俊,Kimitoshi YONEDA
発刊日:
公開日:
キーワードタグ:
Flow accelerated corrosion (FAC) is the major pipe wall thinning phenomena in power plants. The management of pipe wall thinning has been carried out to pipe elements such as elbow, orifice, etc. of the piping system in power plants. In piping system, it is known that several pipe elements which are connected in series may generate swirl flow. Therefore the arrangement of pipe elements is considered to affect thinning phenomena seriously. So the behavior of this swirl flow is one of the major research tar...
英字タイトル:
Evaluation of mass transfer coefficient under swirl flowgenerated by the combination of pipe elements
第10回
鋳造ステンレス鋼配管溶接部における軸方向き裂の 大型振動子探触子による超音波探傷試験とシミュレーション解析
著者:
西川 嘉人,Yoshito NISHIKAWA,石田 仁志,Hitoshi ISHIDA
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Ultrasonic testing is difficult for cast stainless steel which is used as the material of main coolant pipes in pressurized water reactors, because of the ultrasonic scattering by the huge grain of the material. Therefore we performed ultrasonic testing for the axial fatigue crack on welding area in the test piece of the cast stainless pipe, using the double big-size ultrasonic probes which we developed. And we simulated the ultrasonic beam behavior using finite element ultrasonic propagation simulatio...
英字タイトル:
Ultrasonic testing and simulation analysis by the large aperture transducer for axial crack in cast stainless steel pipe weld