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为评价国产燃料棒在较高燃耗水平下的辐照性能,在中国原子能科学研究院燃料与材料检验设施(303热室)对燃耗为40 GW·d/tU的国产压水堆核电站乏燃料棒进行了金相检验。检验内容包括芯块宏观与微观组织、包壳水侧腐蚀与氢化物分布、芯块-包壳相互作用状况等。金相检验结果表明:40 GW·d/tU燃耗下,芯块未发生明显的轮廓变化,气孔率为3.3%·5.8%,晶粒组织为等轴晶,平均晶粒尺寸为7.2μm;Zr合金最大水侧氧化膜厚度为23μm,氢化物分布和含量正常,最大氢含量约为150μg/g,同吋不同部位的包壳氢含量与水侧氧化膜厚度基本呈线性关系,水侧腐蚀处于正常水平;包壳内壁有局部轻微腐蚀,包壳与芯块之间存在间隙,未发生包壳与芯块相互作用情况。
In order to evaluate the irradiation performance of domestic fuel rods at higher fuel consumption level, a test was conducted on the domestic PWR nuclear power plant with a fuel consumption of 40 GW · d / tU at the Fuel and Materials Testing Facility of China Institute of Atomic Energy (Room 303) Fuel rods were metallographic examination. The test contents include macroscopic and microscopic structure of the pellet, corrosion and hydride distribution in the water side of the cladding, and the condition of the pellet-cladding interaction. The results of metallographic examination show that there is no obvious contour change of the pellets under the fuel consumption of 40 GW · d / tU, the porosity is 3.3% and 5.8%, the grain structure is equiaxed and the average grain size is 7.2μm. The maximum thickness of the oxide film on the water side of Zr alloy is 23μm, the distribution and content of hydride are normal and the maximum hydrogen content is about 150μg / g. The hydrogen content in the shell of the Zr alloy has a linear relationship with the thickness of the oxide film on the water side, At the normal level; there is a slight corrosion on the inner wall of the cladding, there is a gap between the cladding and the core, and there is no interaction between the cladding and the core.