Sasahara Akihiro | Nuclear Technology Research Laboratory Central Research Institute Of Electric Power Industry

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概要

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• 同名の論文著者
• Nuclear Technology Research Laboratory Central Research Institute Of Electric Power Industryの論文著者

関連著者

• SASAHARA Akihiro

  Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry

• MATSUMURA Tetsuo

  Material Science Research Laboratory, Central Research Institute of Electric Power Industry

• Sasahara Akihiro

  Nuclear Technology Research Laboratory Central Research Institute Of Electric Power Industry

• Matsumura Tetsuo

  Material Science Research Laboratory Central Research Institute Of Electric Power Industry

• Matsumura Tetsuo

  Central Research Institute Of Electric Power Industry

• Nicolaou Giorgos

  Laboratory Of Nuclear Technology Department Of Electrical And Computer Engineering Faculty Of Engine

• KIYANAGI Yoshiaki

  Hokkaido University

• NICOLAOU Giorgos

  Laboratory of Nuclear Technology, Department of Electrical and Computer Engineering, Faculty of Engi

• KIYANAGI Yoshiaki

  Graduate School of Engineering, Hokkaido University

• Sasahara Akihiro

  Central Research Institute Of Electric Power Industry

• Kiyanagi Yoshiaki

  Hokkaido Univ.

• Kiyanagi Yoshiaki

  Graduate School Of Engineering Hokkaido University

• Kiyanagi Yoshiaki

  Faculty of Engineering, Hokkaido University

• Kameyama Takanori

  Central Research Institute of Electric Power Industry

• NICOLAOU Giorgos

  National Centre for Scientific Research 'Demokritos'

• PAPAIOANNOU Dimitri

  European Commission, Joint Research Centre, Institute for Transuranium Elements

• Kameyama Takanori

  Central Res. Inst. Of Electric Power Ind.

• Papaioannou Dimitri

  European Commission Joint Research Centre Institute For Transuranium Elements

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著作論文

• Chemical Isotopic Analysis of Fission Products in PWR-MOX Spent Fuels and Computational Evaluation Using JENDL, ENDF/B, JEF, and JEFF
• Analyses of Burnup at plutonium Spots in Uranium-Plutonium Mixed Oxide Fuels in Light Water Reactors by Neutron Transport and Burnup Calculations
• Isotopic Analysis of Actinides and Fission Products in LWR High-Burnup UO_2 Spent Fuels and its Comparison with Nuclide Composition Calculated Using JENDL, ENDF/B, JEF and JEFF
• Neutron and Gamma Ray Source Evaluation of LWR High Burn-up UO_2 and MOX Spent Fuels

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