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堆芯模拟是压水堆水力模拟实验研究的关键技术,通常采用燃料组件一一对应的模拟方式,使堆芯流量分配实验数据有一一对应关系。   本文结合秦山核电二期工程介绍了电站压水堆堆芯水力模拟的一般理论和方法。在国内首次应用E.U.Khan压水堆开式栅格堆芯模拟理论,用22棒束模拟原型1717棒束,用特殊研制的内磁式涡轮流量计测量堆芯入口流量分配,微型电导电极测量下空腔流动交混,完成了600 MWe反应堆水力模拟堆芯的设计、实验等工作。

Core modeling is the key technique of pressurized water reactor(PWR) hydraulicsimulation. Generally speaking, an assembly-by-assembly modeling is put intopractice, which makes it possible that the data of flow rate distributionfactors at the core inlet have corresponding relationship.This paper presents the common theory and method of power station PWR corehydraulic modeling in the light of nuclear power project of Qinshan phaseⅡ. For the first time E.U.Khan's open lattice core modeling is used in thecountry. A 22 rod bundle is developed to simulate the 1717 rodbundle of prototype. For the purpose of 600MWe reactor hydraulic simulationtest and core modeling, a turbine especially made and an electrode that arelocated inside the model assemble are used to measure flow rate distributionand flow mixing factors in the lower plenum respectively.

参考文献

[1] R T Berringer;A A Bishop .YAEC-74[Z].,1959.
[2] G Hetsroni.Hydraulic Tests of the San-Onofre Reactor Model[M].WCAP-3296-8
[3] E U Khan.Analytical lnvestigation and Design of a ModelHydrodynamically Simulation a Prototype PWR Core[M].Nucl,1972:16.
[4] 汪利民 .秦山核电二期工程600 MWe压水堆堆芯入口流量分配实验研究[R].成都:中国核动力研究设计院内部报告,1997.
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