原子能科学技术2018，Vol.52Issue(3)：420-426,7.DOI:10.7538/yzk.2017.youxian.0324
国产压水堆核电站40GW·d/tU乏燃料棒金相检验
Metallographic Test of Domestic PWR Nuclear Station Spent Fuel Rod of 40 GW · d/tU Burnup
钱进 1卞伟 1郭丽娜 1郭一帆 1梁政强1
作者信息
- 1. 中国原子能科学研究院反应堆工程技术研究部,北京 102413
- 折叠
摘要
Abstract
In order to evaluate the radiation performance of domestic fuel rods at high burnup level,the metallographic test of a domestic pressurized-water reactor (PWR) nuclear station spent fuel rod with the burnup of 40 GW · d/tU was done in the Fuel and Material Examination Facility (303 hot cell) of China Institute of Atomic Energy (CIAE).The contents of the metallographic test include macro-and micro-structure examination of fuel pellets,waterside oxidation and hydride distribution of cladding,pellet-cladding interaction (PCI) and so on.The test and analysis results show that under the burnup of 40 GW · d/tU,the shape of the pellets is not changed obviously,the range of fuel porosity is 3.3％-5.8％,the grains of fuel are equiaxed crystal,and the average size of these grains is 7.2 μm.Waterside oxidation of the cladding is normal,and the maximum thickness of waterside oxide film is 23 μm.The content and distribution of hydride are normal,the maximum hydrogen content is 150 μg/g and the hydrogen content keeps a proportional relation with the thickness of waterside oxide film nearly.There is a slight localized corrosion in the inner wall of the cladding.The gap of pellets and cladding is existent and the PCI phenomenon is not found.关键词
压水堆核电站/乏燃料棒/高燃耗/辐照后检验/金相检验Key words
pressurized-water reactor nuclear station/spent fuel rod/high burnup/post irradiation examination/metallographic test分类
能源科技引用本文复制引用
钱进,卞伟,郭丽娜,郭一帆,梁政强..国产压水堆核电站40GW·d/tU乏燃料棒金相检验[J].原子能科学技术,2018,52(3):420-426,7.
