【摘要】 目的采用小冲杆测试方法测量高能重离子辐照反应堆压力容器A508-3钢的辐照硬化和脆化特性,为工况条件下反应堆压力容器寿命预测提供实验依据。方法采用兰州重离子加速器提供的高能C⁶⁺离子通过减能装置在290℃条件下开展A508-3钢辐照实验,并在样品表面形成一定厚度、准均匀分布的离位损伤层。通过开展不同辐照剂量辐照样品的小冲杆测试,得到不同辐照剂量A508-3钢的小冲杆载荷-位移曲线。通过对小冲杆测试得到的载荷-位移曲线的分析,测定不同辐照剂量样品的辐照硬化和脆化特性。结果压力容器A508-3钢辐照样品的硬化和脆化随着辐照剂量的增加逐渐增强,0.15dpa以前呈线性增长,而后缓慢增大,约0.2 dpa时达到饱和趋势。结论通过小冲杆测试可以得到离子辐照样品的硬化和脆化行为,A508-3钢辐照硬化和脆化行为具有一致的变化趋势。更多还原

【Abstract】 The hardening and embrittlement characteristics of high-energy heavy-ions irradiated reactor pressure vessel A508-3 steel are measured by small punch test method, which provides experimental basis for the life prediction of reactor pressure vessel under working conditions.The high energy C⁶⁺ ions provided by Heavy Ion Research Facility are used to irradiate A508-3 steel at 290 ℃ by means of energy degrader, and a certain thickness of quasi-uniform damaged layer are formed on the sample surfaces.The load-displacement curves of A508-3 steel with different irradiation doses are obtained by small punch test.Through the analysis of the load-displacement curves obtained from the small punch test, the irradiation hardening and embrittlement characteristics of the samples with different irradiation doses are determined.The hardening and embrittlement of A508-3 steel increased with the increase of irradiation dose.It showed a linear increase before 0.15 dpa, then increased slowly,and reached saturation at about 0.2 dpa.The change trend of radiation hardening and embrittlement is consistent.更多还原