第5回
PaM(原因除去型保全)導入に向けた潤滑油管理の取組みについて
著者:
杉原 雅紀,Masanori SUGIHARA,広瀬 逸夫,Itsuo HIROSE,矢野 裕二,Yuji YANO
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Lubricant management is very important to maintain the integrity of rotating equipment. Lubricant is periodically replaced and monitored on its aging degr adation between replacement times. On the other hand, only the confirmation of specification document has been performed as acceptance inspection in case of new lubricant. However, a comparatively large amount of impurity substances has been found in new lubricant by sample analysis. Therefore, the introduc tion of contamination control of new lubricant ...
英字タイトル:
Application of Contamination Control of Lubricant to Proactive Maintenance
第14回
ショットピーニング時の残留応力緩和挙動に関する検討
著者:
木谷 悠二,Yuji KITANI,柴原 正和,Masakazu SHIBAHARA,生島 一樹,Kazuki IKUSHIMA,山田 祐介,Yusuke YAMADA,西川 聡,Satoru NISHIKAWA,古川 敬,Takashi FURUKAWA,秋田 貢一,Koichi AKITA,鈴木 裕士,Hiroshi SUZUKI,諸岡 聡,Satoshi MOROOKA
発刊日:
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In nuclear power plants, surface treatment including the shot peening is carried out after welding for the prevention of stress corrosion cracking. In this research, the authors developed evaluation systems of the persistence of compressive residual stresses due to shot peening based on the Idealized Explicit FEM which can conduct large-scale non-linear structure analyses in realistic computing time. The developed evaluation system was applied to the analysis of the compressive residual stress due to sho...
英字タイトル:
Study of behaver to relieve residual stress at the time of the shot peening
第9回
ナトリウム冷却型 FBR 向け摩擦攪拌接合補修装置の開発
著者:
加藤 潤悟,Jungo KATOH,森本 将明,Masaaki MORIMOTO,篠原 種宏,Tanehiro SHINOHARA,堀 匠,Takumi HORI,渡部 裕二郎,Yujiro WATANABE,藤谷 泰之,Yasuyuki FUJIYA,道下 幸雄,Yukio MICHISHITA,中田 一博,Kazuhiro NAKATA
発刊日:
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An in-vessel repairing machine for Fast Breeder Reactor (FBR) needs to work under liquid sodium environment. W e have been worked the development of a repairing machine based on Friction Stir Welding (FSW) method. The expe riment of repairing artificial crack in liquid sodium was successful by prototype FSW-repairing machine. In th is report, we also introduce our studies on the particular problems of FSW-repairing such as burr and end hole....
英字タイトル:
Development of a repairing machine based on Friction Stir Welding (FSW) for the sodium coolant Fast Breeder Reactor
第13回
プルトニウム燃焼高温ガス炉の燃料設計及び炉心核熱設計
著者:
後藤 実,Minoru GOTO,稲葉 良知,Yoshitomo INABA,深谷 裕司,Yuji FUKAYA,植田 祥平,Shohei UETA,相原 純,Jun AIHARA,橘 幸男,Yukio TACHIBANA,國富 一彦,Kazuhiko KUNITOMI
発刊日:
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A concept of a plutonium burner HTGR (High Temperature Gas-cooled Reactor) with a high nuclear proliferation resistance has been proposed by Japan Atomic Energy Agency. In addition to the high nuclear proliferation resistance, in order to attain the high burn-up, we propose to introduce a PuO2-YSZ (Yttria Stabilized Zirconia) fuel kernel with ZrC coating to the plutonium burner HTGR. In this study, we conduct design of the coated fuel particle and of the reactor core to confirm the feasibility of the plut...
英字タイトル:
Design Study on Fuel and Reactor Core for Plutonium Burner High Temperature Gas-cooled Reactor
第2回
原子炉容器上蓋管台検査技術のサイジング性評価
著者:
松本 博,Yoshihiro MATSUMOTO,勝又 俊介,Ryosuke KATSUMATA,田中 昌幸,Masayuki TANAKA,泉田 博幸,Hiroyuki IZUMIDA,原田 豊,Yutaka HARADA,村上 龍兒,Ryuji MURAKAMI
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This paper describes the result of demonstration test using WesDyne International's inspection system in terms of its sizing capability of crack from the inner diameter (ID) of PWR RV head penetrations, detectability of the crack e mbedded under repair welding, which was applied for isolation from the primary water environment, and the propagation of ultrasonic wave from the ID penetration to the inside of J-weld. The result of the laboratory tests have demon strated the sizing capabilities of both ultraso...
英字タイトル:
Sizing Capabilities of Crack for the Inspection of PWR RV Head Penetrations
第7回
導管の次世代保安向上新技術調査・評価事業
著者:
樋口 裕思,Yuji HIGUCHI,木林 哲也,Tetsuya KIBAYASHI,白土 忠人,Tadahito SIRATO,重田 隆弘,Takahiro SHIGETA,石川 雅章,Masaaki ISHIKAWA,橋本 義和,Yishikazu HASHIMOTO,渡辺 剛史,Tsuyoshi WATANABE,平井 稔雄,Toshio HIRAI,安達 俊彰,Toshiaki ADACHI,桑原 元希,Motoki KUWAHARA,長沢 圭介,Keisuke NAGASAWA,綱崎 勝,Masaru TSUNASAKI,枇杷友 啓郎,Yoshirou BIWATOMO,古野 俊秋,Toshiaki FURUNO
発刊日:
公開日:
キーワードタグ:
The aim of this study is to research and evaluate new technologies i n the world from the point of view to improve the safety and securi ty of pipeline for gas distribution toward the next generation which can practice the productive maintenance and preventive maintenance....
英字タイトル:
Research and Evaluation of New Technologies to Improve the Maintenance of Pipeline for GasDistribution toward the Next Generation
第6回
導管の次世代保安向上新技術調査・評価事業
著者:
樋口 裕思,Yuji HIGUCHI,木林 哲也,Tetsuya KIBAYASHI,白土 忠人,Tadahito SIRATO,一重田 隆弘,Takahiro SHIGETA,石川 雅章,Masaaki ISHIKAWA,渡辺 剛史,Tsuyoshi WATANABE,今川 隆,Takashi IMAGAWA,平井 稔雄,Toshio HIRAI,桑原 元希,Motoki KUWAHARA,原 裕司,Yuji HARA,長沢 圭介,Keisuke NAGASAWA,綱崎 勝,Masaru TSUNASAKI,枇杷友 啓郎,Yoshirou BIWATOMO,古野 俊秋,Toshiaki FURUNO
発刊日:
公開日:
キーワードタグ:
The aim of this study is to research and evaluate new technologies in the world from the point of view to improve the safety and security of pipeline for gas distribution toward the next generation which can practice the productive maintenance and prevent ive maintenance. ...
英字タイトル:
Research and Evaluation of New Technologies to Improve the Maintenance of Pipeline for GasDistribution toward the Next Generation
第14回
応力改善工法で付与した圧縮残留応力の持続性評価-ショットピーニングを施した溶接継手の熱サイクル及び応力負荷による残留応力変化(第2報)
著者:
西川 聡,Satoru NISHIKAWA,古川 敬,Takashi FURUKAWA,秋田 貢一,Koichi AKITA,鈴木 裕士,Hiroshi SUZUKI,諸岡 聡,Satoshi MOROOKA, ハルヨ ステファヌス,Stefanus HARJO,柴原 正和,Masakazu SHIBAHARA,生島 一樹,Kazuki IKUSHIMA,木谷 悠二,Yuji KITANI,山田 祐介,Yusuke YAMADA
発刊日:
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To validate the FEM simulation technique presented in the previous report, we made pipe butt welded joints between base metals of the same material SUS316L and between base metals of the dissimilar materials SUS316L and STPT370. Shot peening (SP) on the outer surface or the inner surface of these welded joints induces high compressive residual stresses on the surface. After heat treatment with the peak temperature of 623 K was applied to the welded joints, they retained high compressive residual stresses ...
英字タイトル:
Evaluation of the sustainability of compressive residual stress by introduced a stress improvement method (the second report) ?Residual stress change of welded joint with shot peening by thermal cycle and stress loading.
第14回
応力改善工法で付与した圧縮残留応力の持続性評価-理想 化陽解法 FEM を用いたショットピーニング解析手法の開発 (第 1 報)
著者:
山田 祐介,Yusuke YAMADA,柴原 正和,Masakazu SHIBAHARA,生島 一樹,Kazuki IKUSHIMA,木谷 悠二,Yuji KITANI,西川 聡,Satoru NISHIKAWA,古川 敬,Takashi FURUKAWA,秋田 貢一,Koichi AKITA,鈴木 裕士,Hiroshi SUZUKI,諸岡 聡,Satoshi MOROOKA
発刊日:
公開日:
キーワードタグ:
When the steel structure is built such as nuclear power plant, residual stress occurs in or near the welding joint and it may cause the stress collision cracking(SCC). Therefore, as prediction of SCC, surface treatment such as the shot peening(following SP) is carried out in the weld, but the case analyzed about residual stress reforming by the SP does not exist. So, we developed the analysis method that can predict compressive residual stress relaxation behavior during shot peening by modelling dynami...
英字タイトル:
Evaluation of the sustainability of compressive residual stress by introduced a stress improvement method (the first report) -Development of analysis method of the shot peening using idealized explicit FEM
第3回
炉内保全用レーザピーニングシステムの高度化
著者:
向井 成彦,Naruhiko MUKAI,上原 拓也,Takuya UEHARA,末園 暢一,Nobuichi SUEZONO,佐伯 綾一,Ryoichi SAEKI,佐野 雄二,Yuji SANO
発刊日:
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Abstract: Laser peening (LP) is a process to introduce residual compressive stress on metal surface by irradiating laser pulses underwater without any surface preparations. Toshiba has developed and applied LP system to preventive maintenance against stress corrosion cracking (SCC) in nuclear power reactors since 1999. The system is composed of laser oscillators, a beam delivery system, a laser irradiation head, remote handling equipment and a monitor/control system. In the early applications, a rigidly l...
英字タイトル:
Next Generation LP System for Maintenance in Nuclear Power Reactors