Behavior of Cladding Tube under Coolant-Loss Accident Conditions

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概要

• 論文の詳細を見る

• he behavior of cladding tubes, both stainless steel and zircaloy under the post-accidental conditions of coolant loss has been discussed, based on the results of three experiments performed this time. The effect of oxidation in post-accidental steam atmosphere up to temperatures where the cladding tube should burst with the pressure of entrapped fission product gas was found to be negligible. The bursting behavior of tubes containing pre-determined amounts of inert gas cor-responding to the amounts of released fission product gas that should be present in various states of fuel usage was also examined. No effect of corrosion in zircaloy-2 that should affect its strength could be found up to a weight gain corresponding to several years of use under normal operating conditions, either in the burst strength or creep burst behavior.

• 一般社団法人 日本原子力学会の論文

著者

• AOKI Toshimasa

  Atomic Fuel Corp.

• MISHIMA Yoshitsugu

  Univ. of Tokyo, Bunkyo-ku, Tokyo

• TAKAO Zenichiro

  Kobe Steel, Ltd.

• ONO Kenji

  Hitachi Ltd.

• ITO Goro

  National Research Institute for Metals

• KIYOOKA Shoichi

  Tokyo Shibaura Electric Co., Ltd.

• SEKI Yoshitatsu

  Mitsubishi Atomic Power Industries, Inc.

• SUMITOMO Motoo

  Sumitomo Metal Industries, Ltd.

関連論文

• The Development of an Apparatus for Providing Artificial Surface Defects on Inside Surface of Cladding Tubes
• Effect of Poorly Uniform Thickness and Surface Defects on Burst Test Results of Fuel Cladding Tubes
• Behavior of Cladding Tube under Coolant-Loss Accident Conditions

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