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A method of organizing the natural circulation of a liquid metal coolant of a fast neutron nuclear reactor

机译:一种组织快速中子核反应堆液态金属冷却剂自然循环的方法

摘要

The invention relates to the field of nuclear engineering and can be used to organize the natural circulation of liquid metal coolant in the heat sink of a fast neutron nuclear reactor.In order to create a driving pressure of circulation without using pumping equipment and to provide the required direction of natural circulation of the liquid metal coolant in the heat sink circuit of the fast neutron nuclear reactor in the absence of heat transfer from the reactor before filling the pipelines and equipment of the lifting and downing sections of the circuit, they are pre-heated by electric heating to temperatures Tsub1/suband Tsub2/sub, respectively, which are selected from the condition of inequality: ρsub1/sub(Tsub1/sub)·g·ΔHsub1/sub ρsub2/sub(Tsub2/sub)·g·ΔHsub2/sub+ΔP, where: ρsub1/sub(Tsub1/sub) is the density of the liquid metal coolant at temperature Tsub1/subof pipelines and equipment in the lifting section;ρsub2/sub(Tsub2/sub) is the density of the liquid metal coolant at temperature Tsub2/subof pipelines and equipment at the downing section;supΔ/supHsub1/subis the height difference between the inlet and outlet of the lifting section;supΔ/supHsub2/subis the height difference between the inlet and outlet of the downing section;supΔ/supP is the hydraulic resistance of the circuit; g is the acceleration of gravity.The circulation of the coolant in the circuit and the transition to natural circulation mode are carried out simultaneously until the nuclear reactor reaches its rated operating parameters by creating a moving pressure of the circulation due to the difference in densities ρsub1/sub(Tsub1/sub) and ρsub2/sub(Tsub2/sub) of the liquid metal coolant on the lifting and downing sections of the circuit, respectively.
机译:本发明涉及核工程领域,可用于组织快速中子核反应堆散热器中液态金属冷却剂的自然循环。在不使用泵送设备的情况下产生循环的驱动压力并提供快速中子核反应堆散热器回路中液态金属冷却剂自然循环的要求方向,在没有向反应堆传热之前,在填充回路的升降部分的管道和设备之前,反应堆没有传热,它们是预先准备好的。通过电加热将温度分别加热到T 1 和T 2 ,这是从不等式ρ 1 (T 1 )·g·ΔH 1 2 (T 2 )·g·ΔH 2 +ΔP,其中:ρ 1 (T 1 )是管道和设备在温度T 1 时液态金属冷却剂的密度在提升部分;ρ 2 (T 2 )是下降段管道和设备在温度T 2 时液态金属冷却液的密度; Δ H 1 是高度差升降段的入口和出口之间的高度; Δ H 2 是下降段的入口和出口之间的高度差; Δ P是回路的液压阻力; g是重力加速度。冷却剂在回路中的循环和向自然循环模式的转换要同时进行,直到核反应堆通过由于密度ρ的差异而产生的循环运动压力而达到其额定运行参数为止。液态金属冷却剂在升降时的 1 (T 1 )和ρ 2 (T 2 )电路的各个部分。

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