Kai Tetsuya | Research Reactor Institute Kyoto University
スポンサーリンク
概要
関連著者
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YAMAMOTO Shuji
Research Center for Cancer Prevention and Screening, National Cancer Center
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木村 逸郎
京都大学
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Yamamoto Shuji
Research Center For Cancer Prevention And Screening National Cancer Center
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Kanno Ikuo
Department Of Nuclear Engineering Kyoto University
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KIMURA Itsuro
Department of Nuclear Engineering, Kyoto University
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Kai T
Research Reactor Institute Kyoto University
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Fujita Yoshiaki
Research Reactor Institute Kyoto University
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KOBAYASHI Katsutoshi
Japan Atomic Energy Research Institute
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KOBAYASHI Katsuhei
Research Reactor Institute, Kyoto University
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Kai Tetsuya
Research Reactor Institute Kyoto University
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Katsuhei Kobayashi
Research Reactor Institute Kyoto University
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Kobayashi Katsuhei
Research Reactor Institute Kyoto Uninversity
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Kobayashi Katsuhei
Research Reactor Institute Kyoto University
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Yamamoto S
Research Reactor Institute Kyoto University
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Kimura Itsuro
Department Of Aeronautics And Astronautics School Of Engineering
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Cho Hyun-je
Research Reactor Institute Kyoto University
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木村 逸郎
大阪科学技術センター
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YAMANA Hajimu
Research Reactor Institute, Kyoto University
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SHINOHARA Nobuo
Department of Urology, Hokkaido University school of Medicine
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Mitsugashira Toshiaki
Tohoku University
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Mitsugashira Toshiaki
The Oarai-branch Institute For Materials Research Tohoku University
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Mitsugashira Toshiaki
Oarai Lab. Institute For Materials Research Tohoku University
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Mitsugashira Toshiaki
Institute For Materials Research (imr) Tohoku University
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Mitsugashira Toshiaki
The Oarai-branch Institute For Material Research Tohoku University
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Yamana H
Research Reactor Institute Kyoto University
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Yamana Hajimu
Research Reactor Institute Kyoto University
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Shinohara Nobuo
Department Of Materials Science And Engineering Japan Atomic Energy Research Institute
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Yamana Hajimu
Res. Reactor Inst. Kyoto Univ.
著作論文
- Measurements of Neutron-induced Fission Cross Section of Protactinium-231 from 0. 1eV to 10keV with Lead Slowing-down Spectrometer and at 0. 0253eV with Thermal Neutron Facility
- Measurements of Neutron-induced Fission Cross Section of Americium-243 from Thermal Neutron Energy to 15keV Using Lead Slowing-down Spectrometer and Thermal Neutron Facility