OGAWA Yutaka | Japan Atomic Energy Research Institute
スポンサーリンク
概要
関連著者
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OGAWA Yutaka
Japan Atomic Energy Research Institute
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KURATA Yuji
Japan Atomic Energy Agency
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Kurata Y
Japan Atomic Energy Research Institute
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Nakajima Hajime
Japan Atomic Energy Research Institute
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SHINDO Masami
Japan Atomic Energy Research Institute
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SUZUKI Tomio
Japan Atomic Energy Research Institute
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KONDO Tatsuo
Japan Atomic Energy Research Institute
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Saito Teiichiro
Nippon Welding Rod Co. Ltd Research Laboratory
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Ogawa Y
Hokkaido Univ. Sapporo
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Torikai Kinichi
Japan Atomic Energy Research Institute
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FUTAMURA Yoshiaki
Japan Atomic Energy Research Institute
著作論文
- Long-Term Creep Properties of Hastelloy XR in Simulated High-Temperature Gas-Cooled Reactor Helium
- Piping cracks in JPDR. IV. Analysis of cause of cracks found near weld joints connecting reactor vessel nozzle safe-end to pipe.:Analysis of Cause of Cracks Found near Weld Joints Connecting Reactor Vessel Nozzle Safe-End to Pipe