Behavior of Zircaloy Fuel Cladding Tubes

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概要

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• A series of experiments has been performed to obtain information on the behavior of zircaloy fuel cladding tube, indispensable for predicting fuel performance in water reactors.<BR>The results obtained are arranged under the following headings :<BR>(1) Hydride behavior : The effects of stress on non-uniform precipitation, thermal diffusion of hydrogen in zircaloy containing hydrogen beyond terminal solid solubility, and directionality changes by thermal cycling and stress<BR>(2) Deformation behavior : Plastic deformation and fracture behavior under biaxial stress and external-pressure creep<BR>(3) Heat transfer characteristics of oxide film.

• 一般社団法人 日本原子力学会の論文

著者

• MAKI Hideo

  Hitachi Research Laboratory, Hitachi Ltd.

• OOYAMA Masatoshi

  Hitachi Research Laboratory, Hitachi Ltd.

関連論文

• Thermal Diffusion of Hydrogen in Zircaloy-2 Containing Hydrogen beyond Terminal Solid Solubility
• Out-of-Reactor Study on External-Pressure Creep of Zircaloy-2 Fuel Cladding Tubes
• Behavior of Zircaloy Fuel Cladding Tubes
• Plastic Deformation and Fracture Behavior of Zircaloy-2 Fuel Cladding Tubes under Biaxial Stress

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