堆芯损伤状态包括堆芯无损伤、燃料元件包壳破损、燃料过热和燃料熔化等四种。
Core damage states include no core damage, fuel clad failure, fuel overheat and fuel melt.
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.
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.
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