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为了配合秦山核电厂燃料元件堆内考验,用FRAPCON-2程序分析了考验条件下的元件行为。在传热分析中考虑了冷却剂温度沿流道的变化、包壳到冷却剂的传热、水垢引起的温升、氧化膜温升、间隙传热(包括裂变气体释放和燃料重定位影响)、芯块开裂对芯块导热系数修正以及自屏效应等;在强度计算中考虑了包壳内外压力、包壳和
In order to cooperate with the Qinshan nuclear power plant fuel components reactor test, with the FRAPCON-2 program analysis of the components under the test conditions. In the heat transfer analysis, the changes of the coolant temperature along the flow channel, the heat transfer from the cladding to the coolant, the temperature rise caused by the scale, the temperature rise of the oxide film, the heat transfer in the gap (including the fission gas release and the fuel relocation) , Core block cracking on the thermal conductivity correction and self-screen effect, etc .; in the calculation of the strength of the cladding inside and outside the pressure, cladding and