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一、前言Zr-4合金具有优良的物理性能、机械性能,良好的耐蚀性、较低的吸氢率,在现今反应堆的建造中用作压水堆燃料元件的包壳材料。早在五十年代,人们就开始研究 Zr 合金与水蒸汽反应以制定核反应堆安全规则。世界上发生的核电站事故更加显示了制定核安全的迫切性。因而研究在失水事故状态下燃料包壳的氧化行为对于充分利用核能,制定正确的核反应堆安全运行规则具有重要的意义。
I. INTRODUCTION The Zr-4 alloy has excellent physical properties, mechanical properties, good corrosion resistance and low hydrogen absorption and is used as cladding material for pressurized water reactor fuel elements in the construction of today’s reactors. As early as the fifties, people started to study the reaction of Zr alloys with steam to make nuclear reactor safety rules. Nuclear accidents in the world have further shown the urgency of establishing nuclear safety. Therefore, it is of great significance to study the oxidation behavior of fuel cladding in the event of water loss to make full use of nuclear energy and formulate the correct rules for the safe operation of nuclear reactors.