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11回
重イオン照射した Fe-Cr 合金の磁気ヒステリシス特性の 照射温度及び Cr 濃度依存性
著者:
兜森 達彦,Tatsuhiko KABUTOMORI,鎌田 康寛,Yasuhiro KAMADA,小林 悟,Satoru KOBAYASHI,三谷 誠司,Seiji MITANI,渡辺 英雄,Hideo WATANABE
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Magnetic properties of heavy ion irradiated single crystalline Fe Cr films were investigated High quality Fe 20%Cr 001 films with a thickness of 30 nm were prepared by electron beam deposition and irradiated by 2 4MeV Cu2+ ions at various temperatures and magnetization curves were measured using a VSM Micro fabricated films and Fe Cr film with Cr concentration gradient 0% 13% were also prepared and magnetic domain struct ures were observed using a Kerr microscope The coercivity of Fe 20%Cr increased by ...
英字タイトル:
The irradiation temperature and Chromium concentration dependence of the magnetic properties of heavy-ion irradiated Iron-Chromium alloys
解説記事
長期停止後の高速増殖原型炉「もんじゅ」の試運転再開について
著者:
仲井 悟,Satoru NAKAI,金子 義久,Yoshihisa KANEKO,向 和夫,Kazuo MUKAI
発刊日:
公開日:
1.はじめに高速増殖原型炉「もんじゅ」は、平成7年12月の2次主冷却系ナトリウム漏えい事故以降、約14年半の長期にわたり停止状態であった。長期停止状態にある「もんじゅ」の試運転再開に向け、社会的な受容の確立、トラブル時の迅速な対応を含めた運転管理の向上、透明性の向上をはじめとした各種取り組みを行ってきた。保全の分野においては、ナトリウム漏えいに係る安全性の向上を目的とした改造工事、長期間停止しているプラントを再開するための設備の健全性確認、停止期間中の各種トラブル発生で顕在化した保守管理の問題を解決す......
第5回
長期間使用した9Cr系鋼構造物の電気化学計測を用いたじん性評価
著者:
西川 聡,Satoru NISHIKAWA,大北 茂,Shigeru OHKITA,山口 篤憲,Atsunori YAMAGUCHI
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The weld metal of modified 9Cr-1 Mo steels is most low toughness in its MIG weld joint. It is necessary to pay attention to the toughness of weld metal because of securing to ughness of weld joint. The weld metal of precipitated Laves phase after long-term thermal aging decreased toughness. Peak of the current density (Ip) in the electrochemical t echnique was appeared in the weld metals of precipitated a lot of large Laves phase. It seemed that appearance of lp was caused by the dissolution of the Lave...
英字タイトル:
Electrochemical technique for toughness evaluation on 9Cr type steel components by long-term used
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
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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-