更新情報
第17回
Anisotropic distribution of solute elements in ion - irradiated reactor pressure vessel model alloy
著者:
Ba Vu Chinh NGUYEN,Kenta MURAKAMI, Phongsakorn PRAK TOM, Liang CHEN,(長岡技科大)
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atom probe tomography dislocation loop ion irradiation orientation calculation solute elements
Ba Vu Chinh NGUYEN,Kenta MURAKAMI, Phongsakorn PRAK TOM, Liang CHEN,(長岡技科大)
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公開日:
キーワードタグ:
atom probe tomography dislocation loop ion irradiation orientation calculation solute elements
Atom probe tomography (APT) has been performed on Fe-1.4Mn0.6Ni (at%) model alloy to study solute elements behavior under 2.8 MeV Fe ions at 400 0C. Orientation imaging microscopy (OIM) analysis is applied on the detector hit map to determine the pole figure supporting for orientation calculation. The three-dimensional images show that Mn and Ni solute atoms are distributed close to some certain planes, namely <111> and <100> families. This arrangement of solute atoms on the habit planes of interstitial loo...
英字タイトル:
Anisotropic distribution of solute elements in ion - irradiated reactor pressure vessel model alloy
英字タイトル:
Anisotropic distribution of solute elements in ion - irradiated reactor pressure vessel model alloy
第17回
IRIDMを活用した原子力複合災害を考慮した事業継続計画の提案
著者:
荒木 浩考,(長岡技科大),村上 健太,(東京大)
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Business Continuity Plan IRIDM Nuclear Emergency Preparedness
荒木 浩考,(長岡技科大),村上 健太,(東京大)
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Business Continuity Plan IRIDM Nuclear Emergency Preparedness
Nowadays, companies and educational institutions are required to prepare and respond to natural disasters with Business Continuity Plans (BCP). However, many of the BCP currently being formulated focused only on the natural disasters. Therefore, this study aims to develop the framework of BCP and its formulation method considering the compound risk of nuclear and natural disasters by utilizing the IRIDM process. The IRIDM process is to optimize decision-making for continuously improving the safety of Nuclea...
英字タイトル:
Development of Business Continuity Plan Considering the Compound Risk of Nuclear Disaster Based on IRIDM process
英字タイトル:
Development of Business Continuity Plan Considering the Compound Risk of Nuclear Disaster Based on IRIDM process
第17回
Radiation-Induced Volume Expansion in Concrete Aggregate Minerals Studied by Ion Irradiation and Step Height Measurement
著者:
Muammar Hawary Patris, Kenta Murakami, Luu Vu Nhut, Xinrun Chen,(長岡技科大), Ippei Maruyama,(名古屋大), Takahiro Ohkubo,(千葉大), Kiyoteru Suzuki,(三菱総研)
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aggregate minerals amorphization Ion irradiation radiation-induced volume expansion
Muammar Hawary Patris, Kenta Murakami, Luu Vu Nhut, Xinrun Chen,(長岡技科大), Ippei Maruyama,(名古屋大), Takahiro Ohkubo,(千葉大), Kiyoteru Suzuki,(三菱総研)
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aggregate minerals amorphization Ion irradiation radiation-induced volume expansion
Long-term radiation exposure can cause damage of concrete structures due to the volume expansion of the aggregate minerals. In this study, granite, sandstone, and tuff were irradiated with 2.8 MeV Fe2+ at room temperature to different level of ion fluences. Step height measurement was conducted to quantify the volume change. It was found that the swelling of all minerals saturated at around 300 nm. Tuff, which contains almost all silica, exhibited the fastest swelling, among others.
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第17回
レベル3PRAによる立地地域の被ばくリスクプロファイル評価
著者:
山本 啓太,(長岡技科大),村上 健太,(長岡技科大・東京大)
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Disaster prevention Level3 PRA
山本 啓太,(長岡技科大),村上 健太,(長岡技科大・東京大)
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Disaster prevention Level3 PRA
In Japan, PAZ -Precautionary Action Zone- and UPZ -Urgent Protective action planning Zone- are decided. On the other hand, there is a big typhoon in summer and heavy snow in winter in Japan. They might prevent citizen to protect from radioactive materials. Therefore, it is important to think evacuation in such a situation.
This study uses OSCAAR -Off Site Consequence Analysis code for Atmospheric Release in Reactor Accident- that is developed by JAEA -Japan Atomic Energy Agency. OSCAAR can evaluate exposure...
英字タイトル:
Evaluating exposure risk profile around NPP by Level3 PRA
英字タイトル:
Evaluating exposure risk profile around NPP by Level3 PRA
第16回
劣化メカニズムに基づく中性子束効果の検討
著者:
村上 健太,(長岡技科大)
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cascade damage diffusion irradiation embrittlement neutron flux effect radiation defects reactor pressure vessels
村上 健太,(長岡技科大)
発刊日:
公開日:
キーワードタグ:
cascade damage diffusion irradiation embrittlement neutron flux effect radiation defects reactor pressure vessels
"Flux effects” on irradiation embrittlement in reactor pressure vessel materials is discussed in detail considering the interaction between two cascade damage occurred nearby. When no nano-scale structure exists nearby the cascade damages, flux effect can be categorized into three physical phenomena related to different irradiation-induced defects interaction. Interaction between a cascade damage and nano-scale structures, such as solute atom clusters, is important to model the growth phase of these structu...
英字タイトル:
Mechanism-based discussion on flux effect to RPV embrittlement
英字タイトル:
Mechanism-based discussion on flux effect to RPV embrittlement