轻水反应堆(LWR)用包壳材料研究进展

Research Progress on Cladding Materials Used for Light Water Reactor

轻水反应堆(LWR)是国际上多数核电站采用的堆型。锆具有良好的加工性能,优良的机械性能,较高的熔点、优异的耐蚀性能及核性能,被用作燃料包壳和堆芯结构材料,是发展核电及核动力舰船不可替代的关键结构材料和功能材料。随着核电技术的发展,对堆芯包壳材料性能提出了更高的要求,综述了核用锆合金包壳材料的国内外研究和使用现状以及新型SiC包壳材料的研发现状。总体来说,锆合金在未来几十年内仍是核反应堆包壳材料的主要用材,开展新合金的研发,不断提升锆合金的性能是世界各国研究者共同的目标;适时加大投入力度,强化条件建设,就能加快具有国内自主知识产权锆合金的产业化步伐,可最终实现核电及核动力用锆合金材料的自主化;SiC材料具有更高的熔点、更好的耐腐蚀性能,是一种极具应用潜力的材料,有可能成为第4代核反应堆的包壳材料,但还需投入大量研究。

Light water reactor（LWR） is a major type of nuclear power reactor in the world. Because of low neutron ab- sorption, good corrosion resistance, and good mechanical properties, zirconium alloys are the key structural materials and functional materials for LWR power used as the cladding materials of fuel elements and other structural materials. With the development of nuclear power technology, the higher performances of the cladding material are needed, this paper reviews the research and application progress of nuclear zirconium alloy cladding and the research and development of new SiC cladding materials. In general, zirconium alloys are still the main structural materials in nuclear reactor in the coming decades, continuous R＆D and improved performance of new zirconium alloys are a common goal of researchers around the world ; it is necessary to increase investments and strengthen the support with human resources and financial input in order to accelerate the pace of industrialization of zirconium alloys with Chinese independent intellectual property rights; with higher melting point and better corrosion resistance requirement, SiC is a potential material for cladding of fourth genera- tion nuclear reactor, but also needs to invest a lot of research.