基于核电设计准则的第三代压水堆与高温气冷堆核电技术安全性比较研究

Comparative Study on Nuclear Power Technology Safety of Third Generation PWR and High Temperature Gas Cooled Reactor Based on Nuclear Power Design Criteria

随着我国社会经济的飞速发展,我国的科学技术水平也是得到了飞速提升,尤其是核电技术快速发展。文章明确阐述了我国第三代以及第四代核电技术的分类。其中,第三代核电是以第三代压水堆(AP1000)为基础,讲述第三代核电技术的非能动安全性。第四代核电技术主要是以温气冷堆为基础,讲述了第四代核电技术中所新添加的固有安全性的几种表达方法,通过比较与研究得出结论。从安全性而言,第四代核电技术的固有安全性更加优秀,在材料、结构等方面也有着明显的提升。

With the rapid development of China’s social economy,China’s scientific and technological level has also been rapidly improved,especially nuclear power technology.This paper briefly explains several classifications of China’s third and fourth generation nuclear power skills.The third generation nuclear power is based on the third generation pressurized water reactor(AP1000),which describes the passive safety of the third generation nuclear power technology.The fourth generation nuclear power technology is mainly based on warm gas cooled reactor.The following basically describes several expression methods of inherent safety newly added in the fourth generation nuclear power technology.Through comparison and research,it can be seen that the inherent safety of the fourth generation nuclear power technology is better in terms of safety,and there are obvious improvements in materials,structures,etc.