锆合金主要用作核反应堆燃料元件的包壳材料及其他堆内构件。
Zirconium-base alloys are used primarily as fuel cladding material and other core structure material in water cooled nuclear power reactors.
反应堆燃料元件的裂变气体释放率测量是辐照后检验的一项重要内容，它对于评价燃料元件的性能起着重要作用。
Fission gas release measurement of reactor fuel rods is one of the main issues of post-irradiation examination, which plays a key role to the evaluation of fuel performance.
锆合金作为轻水核反应堆燃料元件的包壳材料已得到了广泛的应用并积累了丰富的经验，因而仍被列为SCWR潜在的应用材料。
As a light water nuclear reactor fuel cladding material, Zr alloy has been wide used and its application experience accumulated, hence it is the potential materials for SCWR.
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