138件が見つかりました。

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第10回
非常用復水器を用いた過酷事故防止策に関する研究
著者:
下江 知弘,Tomohiro SHIMOE,奈良林 直,Tadashi NARABAYASHI,辻 雅司,Masashi TUJI,千葉 豪,Go CHIBA
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In this study, we aimed to quantitatively evaluate cooling capacity of isolation condenser (IC) for core cooling in Fukushima Daiichi Nuclear Plant Unit 1. In order to evaluate cooling capacity, we calculated decay heat which was emitted from core. We used the data of nuclear fuel and rated thermal power which is released by TEPCO. Analysis was conducted with TRAC code. We made an experiment in order to check input data for IC. Because analysis data was close to experimental data, we made sure of valid...
英字タイトル:
Study of Easing Severe Accident by Using Isolation Condenser
第10回
非破壊評価の観点から見た 原子力発電所機器の疲労割れ管理方法に関する考察
著者:
青木 孝行,Takayuki AOKI,高木 敏行,Toshiyuki TAKAGI
発刊日:
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System safety is considered to secure safety in a comprehensive manner as an entire plant by multiple elemen ts serving an entire plant for a common purpose of safety and an interdependent relationship among elements. nder this concept, we considered how the scheme of fatigue crack management in nuclear power plants should b e and also considered the problems to be solved to establish the effective and efficient management system....
英字タイトル:
Conderation onHow to Manage Fatigue Cracking in Nuclear Power Plants from the viewpoint of Non-destructive Evaluation
第10回
高温用薄膜UTセンサを用いた 高精度な厚さ測定・減肉傾向監視技術の開発 Development of thickness measurement and thickness trend monitoring
著者:
藤田 直樹,Naoki FUJITA,関 伊佐夫,Isao SEKI,松浦 貴之,Takayuki MATSUURA,山本 裕子,Yuko YAMAMOTO,黒川 政秋,Masaaki KUROKAWA
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In order to solve the problems of the thickness measurement, we have developed a thin-film UT sensor having excellent high-temperature durability and conformability in thin film form. In this paper, it was confirmed that the accuracy of thickness measurement for both complex geometries and plates at high-temperature was equivalent to the accuracy of conventional thickness measurement methods. It was also confirmed that the durability at high temperature and for temperature change in the actual equipmen...
英字タイトル:
technology using high-temperature thin-film UT sensor
第10回
高精度品質管理のための溶接構造体形状制御に関する検討
著者:
小林 真治,Shinji KOBAYASHI,岡野 成威,Shigetaka OKANO,望月 正人,Masahito MOCHIZUKI
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It is known that weld distortion has negative influence on structure integrity. Therefore, it is important for ensuring structure strength and reliability to control weld distortion appropriately. Especially, development of various countermeasures against weld distortion is desirable for emergent repair work in large-scale accident such as earthquakes. As one of useful countermeasure against angular distortion, in-process control welding with reverse-side heating was proposed however validation of the ...
英字タイトル:
Study on Shape Regulation Technique of Weld Structure for Good Quality Control
第10回
高経年化技術評価の高度化 －原子炉圧力容器の健全性評価
著者:
勝又 源七郎,Genshichiro KATSUMATA,眞崎 浩一,Koichi MASAKI,小坂部 和也,Kazuya OSAKABE,西川 弘之,Hiroyuki NISHIKAWA,勝山 仁哉,Jinya KATSUYAMA,西山 裕孝,Yutaka NISHIYAMA,鬼沢 邦雄,Kunio ONIZAWA
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To assure the structural integrity of a reactor pressure vessel (RPV) is known as one of the critical issu es to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment methods for RPV integrity, stipulated in the codes and standards, have been endorsed by the regulatory body. Authors h ave initiated extensive research on the improvement of structural integrity assessment methods of RPVs. I this paper, we describe some research results obtained from the second-year activity...
英字タイトル:
Study of System Safety Evaluation on LTO of National Project Structural Integrity Assessment of Reactor Pressure Vessels
第10回
高経年化評価研究に係る実機プラントの利用に関する研究
著者:
榊原 安英,Yasuhide SAKAKIBARA,矢田 浩基,Hiroki YADA
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(Times New Roman 10pt) should be about 150 words. How to use the real materials of the Nuclear Power Plant during decommissioning stage are studied and discussed for a research of ageing management for safe long term operating. Moreover the real structural materials of “Fugen” Power Station during decommissioning stage has been performed to study for the research of ageing management. ...
英字タイトル:
Research of using structural materials of decommissioning Nuclear Power Plant for technical evaluation of ageing management for safe long term operating
第10回
高速増殖炉ＳＧ伝熱細管のＬＤＩによる急速減肉に関する研究
著者:
加藤 慶輔,Keisuke KATO,奈良林 直,Tadashi NARABAYASHI,辻 雅司,Masashi TSUJI,千葉 豪,Go CHIBA,大島 宏之,Hiroyuki OHSHIMA,栗原 成計,Akikazu KURIHARA,内堀 昭寛,Akihiro UCHIBORI
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Wastage phenomena occur when a heat transfer tube is failed in a Steam Generator (SG) of Fast Breeder Reactor (FBR) and its mechanism is still unexplained. We focused on Liquid Droplet Impingement Erosion (LDIE) as a factor of the wastage phenomena and performed a basic study with a partial mock-up water test simulating a piping group in SG for quantitative evaluation of LDIE. First, we did visualization tests of high pressure and high speed jet into water. The test section consists of a failure heat ...
英字タイトル:
Study on Rapid Wastage due to Liquid Droplet Impingement on Heat Transfer Tube in SG of Fast Breeder Reactor
第10回
ＳＭ４９０Ａ鋼の磁化曲線と磁気ＡＥとの相関についての検討
著者:
安部 正高,Masataka ABE
発刊日:
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キーワードタグ:
Magneto-Acoustic Emission (MAE) is stress pulses observed during dynamic magnetization process of ferromagnetic material, which is caused by abrupt and discontinuous motion of magnetic domain wall pinned by inclusions, voids, dislocations, grain boundaries etc. It is known that the incidence of MAE has significant correlation with the rate of magnetization change, so that the characteristics of MAE depend on the applied stress because of Magneto-Elastic Coupling (MEC). In this paper, we examine the cor...
英字タイトル:
Study on Relation between Magnetization Curve and Magneto-Acoustic Emission of SM490A Steel
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