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反应堆压力容器(RPV)是核电站中不可更换、并直接关系到电站安全和经济方面的关键部件,其服役期间主要的问题是在长期高温、高压及中子辐照的环境运行下引起的材料脆化,因此,对RPV材料辐照脆化的研究成为反应堆工程研究的热点问题之一。但在RPV材料辐照脆化的研究中,往往会因为标准样品的尺寸过大,造成一系列的困难,如:试验辐照孔道小试验成本高、放射性高可操作性不强等。本文作者即针对该问题,在调研国外小样品冲压(SP)研究技术的基础上,开发出高低温小样品测试装置(图1),并在-160～23℃的温度范围内对国产RPV钢进行了SP测试,最后将SP测试结果与标准试样结果进行了对比拟合。结果表明:国产A508-3钢的SP测试屈服特征值(Ps/B2)和抗拉特征值(Pmax/B2)随着温度
Reactor pressure vessels (RPVs), which are not replaceable in nuclear power stations and are directly related to the safety and economic aspects of a power plant, are the major problems during service. The material problems caused by long-term high temperature, high pressure and neutron irradiation Therefore, the research on the radiation embrittlement of RPV materials becomes one of the hot issues in the research of reactor engineering. However, in the research of radiation embrittlement of RPV materials, often due to the size of the standard sample is too large, resulting in a series of difficulties, such as: small diameter of the test irradiation tunnel high cost, high radioactivity maneuverability and so on. Based on the investigation of foreign small sample stamping (SP) research technology, the author of this paper developed a small and high temperature sample testing device (Figure 1), and made the domestic RPV steel The SP test was carried out. Finally, the SP test results were compared with the standard test results. The results show that the SP test yield characteristic value (Ps / B2) and tensile characteristic value (Pmax / B2) of domestic A508-3 steel vary with the temperature