第三代PWR核电站1E级热缩套管辐照老化研究

Study on Radiation Aging of Class 1E Heat Shrinkable Tube of the Third-Generation PWR Nuclear Power Plant

对第三代压水堆(PWR)核电站1E级热缩套管分别进行了β射线和γ射线9个不同剂量下的辐照老化试验,测得热缩套管的机械性能。在辐照老化试验过程中,以断裂伸长率作为热缩套管受射线辐照老化后损伤的评定参数;当热缩套管在一定剂量的β射线辐照后和另一剂量的γ射线辐照后的断裂伸长率相同时,则认为两种剂量是等效的。根据测试结果,对断裂伸长率随辐照剂量的变化情况进行曲线拟合,得到热缩套管在两种不同类型射线辐照下的等效比例关系,为第三代PWR核电站1E级壳内热缩套管的研发及质量鉴定试验条件提供了参考依据。

The thermal shrinkage tube of the third⁃generation PWR nuclear power plant was irradiated by beta ray and gamma ray at 9 different doses.The mechanical properties of thermal shrinkage tube were measured.In the process of radiation aging test,crack elongation is used as the parameter to evaluate the damage of heat⁃shrinkable tube after ra⁃diation irradiation.When the elongation at break of thermal⁃shrinkable tube is the same after a given dose of beta radi⁃ation as it is after another dose of gamma radiation,the two doses are considered to be equivalent.According to the test results,the curve fitting of elongation at break with the change of radiation dose is carried out,and the equivalent proportional relations of heat⁃shrinkable casing under two different types of radiation irradiation are obtained.It pro⁃vides a reference for the research and development of the 1E class in containment heat shrinkable tube of the third⁃generation PWR nuclear power plant and the test conditions of quality evaluation.