摘要
压力容器是压水堆核电站全寿期不可更换的关键部件,是核电站安全与寿命的决定因素之一。在长期服役过程中,引起压力容器性能下降的最主要因素是长时间大剂量高能量中子的辐照。辐照将引起压力容器材料韧性降低、脆性升高,从而增加压力容器脆性断裂的潜在危险。因此,压力容器材料抗辐照脆化能力一直是该领域国内外关注的焦点之一。文章针对国产压力容器材料,开展了一定剂量水平(约3×1019n/cm2,E≥1 M eV)的研究堆加速辐照考验,进行了辐照后材料力学性能测试分析,包括冲击性能,动态断裂韧性,以及疲劳性能。同时,将辐照后性能测试结果与辐照前进行对比,分析评价了国产压力容器材料的抗辐照性能。
Pressure vessel is the critical and unchangeable component of the PWR during its service lifetime, which determines the lifetime of nuclear power plant. The property decline of pressure vessel is mainly caused by large dose and high energy neutron irradiation during the long term service. Irradiation can reduce the toughness and increase the brittleness of the pressure vessel materials, thus raising the potential risk of brittle fracture. So irradiation embrittlement resistance of pressure vessel materials has been the focus in the field all over the world. The irradiation test ( - 3 ×10^19 n/cm2 , E≥1 MeV) in research reactor of the pressure vessel material has been carried out. And the mechanical performances have been tested and analyzed after neutron irradiation, including impact property, dynamic fracture toughness, and fatigued property. Meanwhile, by comparing the properties of un-irradiated and irradiated material, we can evaluate the irradiation embrittlement resistance of the pressure vessel material.
出处
《中国材料进展》
CAS
CSCD
2011年第5期7-10,33,共5页
Materials China
基金
国家重点基础研究发展计划(2011CB610503)
国家自然科学基金(10975194)资助项目
关键词
压力容器
中子辐照
辐照脆化
pressure vessel
neutron irradiation
irradiation embrittlement