（九州大）
著者に関連した記事は4件です。
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第16回
圧力容器モデル合金の照射脆化に及ぼすＭｎ，Ｎｉ添加効果
著者:
渡邉 英雄,入江 拓也,合屋 佑介,（九州大）
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Cs corrected TEM Cu precipitate dislocation loop STEM-EDS
渡邉 英雄,入江 拓也,合屋 佑介,（九州大）
発刊日:
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Cs corrected TEM Cu precipitate dislocation loop STEM-EDS
The neutron irradiation of Fe based model alloys and steels leads to an increase in the ductile-to-brittle transition temperature (DBTT) with a decrease in the upper shelf energy. It is well known that the Cu content has a strong influence on the embrittlement phenomena; especially, the Cu-rich precipitates have been thought to be directly responsible for the embrittlement. In contrast, mechanical property studies for the steels with different Cu levels have shown that so-called matrix defects are dominant ...
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Effects of Mn, Ni addition on radiation induced hardness in RPV model alloys
英字タイトル:
Effects of Mn, Ni addition on radiation induced hardness in RPV model alloys
第15回
宇宙線ミュオグラフィによるインフラ設備の劣化探査用検出器の開発
著者:
永田 悠太,金 政浩,Kullapha Chaiwongkhot,小森 智博,寳来 悠,渡辺 幸信,（九州大）
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Cosmic-ray Muon Infrastructure Building Survey Muography Muon Radiography Radiation Detector
永田 悠太,金 政浩,Kullapha Chaiwongkhot,小森 智博,寳来 悠,渡辺 幸信,（九州大）
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Cosmic-ray Muon Infrastructure Building Survey Muography Muon Radiography Radiation Detector
Muography is an imaging technique using cosmic-ray muons. The principle of this technique is similar to that of X-ray radiography. However, the muography can be applied to much larger object, since the muon has high penetrating power. We have developed a portable prototype muography detector for investigation of infrastructure degradation. Through some feasibility measurements, it was found that long measurement time is required to investigate degradation. To shorten the measurement time, we have designed a...
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Development of Muography Detector to Investigate Degradation for Infrastructure Buildings
英字タイトル:
Development of Muography Detector to Investigate Degradation for Infrastructure Buildings
第15回
我が国におけるナトリウム冷却高速炉の安全研究の成果と方向性
著者:
久保 重信,神山 健司,（JAEA）,守田 幸路,（九州大）
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Core Disruptive Accident (CDA) In-vessel Retention (IVR) Reactor Safety Severe Accident Sodium-cooled Fast Reactor (SFR)
久保 重信,神山 健司,（JAEA）,守田 幸路,（九州大）
発刊日:
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Core Disruptive Accident (CDA) In-vessel Retention (IVR) Reactor Safety Severe Accident Sodium-cooled Fast Reactor (SFR)
Severe accidents of sodium-cooled fast reactors (SFRs), which is called core disruptive accidents (CDA), are categorized into typical accident phases, i.e., initiating phase, transitions phase, and material relocation and cooling phase. In recent years, experimental data are accumulated and safety analysis codes are developed focusing on the later phases of accidents. This is because achievement of in-vessel retention (IVR) utilizing superior characteristics of sodium coolant is one of the important objecti...
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Outcome and Direction of Safety Research for Sodium-cooled Fast Reactors in Japan
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Outcome and Direction of Safety Research for Sodium-cooled Fast Reactors in Japan
This research was conducted in cooperation with Kyudenko New Energy Co., Ltd., to measure deformation on wind turbine blades and gather actual data on wind conditions for Wind Turbine #10 of the Kushikino Reimei Wind Farm (in operation since Nov. 2012), in Kushikino, Kagoshima Prefecture. Based on the gathered measurement data, the wind direction that most impacted the structural strength of the turbine was identified, and the data was analyzed in detail. To examine into the failure analysis method based on...
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Large-eddy simulation of airflow over complex terrain and application to the wind turbine safety management
英字タイトル:
Large-eddy simulation of airflow over complex terrain and application to the wind turbine safety management