38件が見つかりました。

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第8回
福島第一原子力発電所事故の経緯
著者:
小林 正英,Masahide KOBAYASHI
発刊日:
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キーワードタグ:
The outlines of Fukushima-daiichi accident were shown in this report. The outline is composed of two parts. On e part is the period from the earthquake to the tsunami, and the other is after the tsunami. Fist part shows t hat the mitigation system and the barrier integrity of Fukushima-daiichi unit 1 to 3 were operable during this period. This result shows that the cause of the Fukushima-daiich accidents were an influence by the tsunami....
英字タイトル:
Outline of the Fukushima-Daiichi Accident
第8回
設備余寿命予測に関する研究 -遺伝的アルゴリズムによる最適予測法-
著者:
陳山 鵬,Ho JINYAMA,小出 悠貴,Yuki KOIDE,李 可, Ka Li,薛 紅涛,Hongtao XUE,里永 憲昭,Noriaki SATONAGA
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Rolling bearing is the most part used in rotating machinery of industrial plant. The condition diagnosis technology of rolling bearing is very important and indispensable for the plant safety and operation stability. The purpose o f this study is to improve the accuracy of the life prediction for a rolling bearing. The paper proposes a searchin g method for the optimum mathematic function for the high accurate prediction by using the genetic algorithms (GA)....
英字タイトル:
Life Prediction of Rolling Bearing Using Genetic Algorithm
第8回
配管減肉管理改善の為の原子力・火力規格の比較分析
著者:
鈴木 翔太,Shota SUZUKI,中村 隆夫,Takao NAKAMURA
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Abstract: The pipe rupture accident by FAC (Flow Accelerated Corrosion) at Mihama Unit3 of The Kansai Electric Power Company made the Japanese utilities recognize the significance of pipe wall thinning in plant life cy cle management. In Japanese PWR, BWR, and thermal power plant, the pipe wall thinning is managed under individual codes. This paper studies the differences of wall thinning management in the codes and their reasons cl early. Quantitative analysis is performed based on the data in the report ...
英字タイトル:
Analysis of comparison between the codes of nuclear and thermal power plantfor improving pipe wall thinning management
第8回
高経年化対策に必要な材料照射相関則の構築
著者:
森下 和功,Kazunori MORISHITA,山本 泰功,Yasunori YAMAMOTO,泉 裕太,Yuta IZUMI,渡辺 淑之,Yoshiyuki WATANABE
発刊日:
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キーワードタグ:
1.はじめに方法である. 例えば運転開始 60 年後の材料劣化の程度を知りたいとしても,実際の照射場を使ったのでは, 軽水炉高経年化対策のひとつに,原子炉圧力容器鋼 材料照射データの取得に 60年もかかってしまう. そこ の中性子照射脆化対策がある.これは,中性子照射にで,中性子エネルギーや中性子束の高い代替の「加速」 よって徐々に劣化する原子炉圧力容器鋼に対する保全照射場を使うことにより,60年よりも短い年数で材料 計画策定を意味するが,このとき必要になる技術課題照射データを取得する.しかしながら,こう......
英字タイトル:
Establishment of the irradiation correlation rules of reactor materialstowards the advanced plant life management
第8回
高速噴霧流による液滴衝撃エロージョンに関する研究(減肉速度の評価と速度依存性)
著者:
林 貫人,Kanto HAYASHI,濱 大地,Daichi HAMA,山縣 貴幸,Takayuki YAMAGATA,高野 剛,Tsuyoshi TAKAMO,藤澤 延行,Nobuyuki FUJISAWA
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The erosion rate of aluminum material by liquid droplet impingement erosion is studied by using high speed spray. In order to propose an accurate prediction method, a new experimental data are obtained by using the spray erosion larger than the scale of specimen, which allo ws a constant erosion rate, while it is not for the previous method. The new experimental data shows that the erosion rate is proportiona l to the power of 7 of the droplet velocity, which results in a highly accurate prediction method...
英字タイトル:
Investigation on Liquid Droplet Impinging Erosion by High-Speed Spray(Evaluation of Erosion Rate and Its Velocity Dependency)
第8回
高速増殖原型炉「もんじゅ」の保全
著者:
仲井 悟,Satoru NAKAI,内橋 昌也,Masaya UCHIHASHI,金子 義久,Yoshihisa KANEKO
発刊日:
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The sodium leak accident in a secondary main cooling system of prototype fast breeder reactor (FBR) Monju was occurred on December 8th in 1995 and the Monju has shut down since that. After the establishment of public acceptance, improvement of operational procedure, countermeasures to sodium leakage, Monju restarted on May 6“ 2010. The integrity confirmation of water and steam, turbine system is underway toward the 40% rated power confirmation test which confirm the whole plant performance. FBR can breed ...
英字タイトル:
Maintenance Activity of Prototype FBR Monju
第8回
高速増殖炉原子炉容器のクリープ疲労に関する信頼性評価手法の開発
著者:
岡島 智史,Satoshi OKAJIMA,浅山 泰,Tai ASAYAMA,千年 宏昌,Hiromasa CHITOSE,町田 秀夫,Hideo MACHIDA,横井 忍,Shinobu YOKOI,神島 吉郎,Yoshio KAMISHIMA
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An evaluation method of the occurrence probability of a through-wall crack in a reactor vessel of a fast breeder reactor due to fatigue-creep interaction has been proposed. Input data were p repared for a trial evaluation and the proposed evaluation method was applied. The result was c ompared with the allowable occurrence probability derived from the safety requirements for FBR....
英字タイトル:
Development of a Reliability Evaluation Method for Fatigue-Creep Interaction Failure of an FBR Reactor Vessel 髙屋 茂 Shigeru TAKAYA
第8回
高速炉用 9Cr フェライト系耐熱鋼における溶接 HAZ 部の組織解析
著者:
岩田 満直,Mitsunao IWATA,杉山 雄一,Yuichi SUGIYAMA,村田 純教,Yoshinori MURATA,高屋 茂,Shigeru TAKAYA
発刊日:
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Microstructural states of metallic materials can be expressed by system free energy, and the estimation of the system free energy is useful for damage analysis of the materials. In this study, chang e with creep time in the system free energy of the FG-HAZ in 9Cr heat resistant ferritic steels is estimated on the basis of a series of experiments such as chemical analysis by using extracted resid ues, X-ray diffraction, and scanning transmission observations. The change in the system free energy is expresse...
英字タイトル:
Microstructural analysis of HAZ in the welded joints of 9Cr heat resistantferritic steels for fast reactor
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