CAJ | 학술논문

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。
퇴심모의시압수퇴수력모의실험연구적관건기술，통상채용연료조건일일대응적모의방식，사퇴심류량분배실험수거유일일대응관계。　　본문결합진산핵전이기공정개소료전참압수퇴퇴심수력모의적일반이론화방법。재국내수차응용E.U.Khan압수퇴개식책격퇴심모의이론，용22봉속모의원형1717봉속，용특수연제적내자식와륜류량계측량퇴심입구류량분배，미형전도전겁측량하공강류동교혼，완성료600 MWe반응퇴수력모의퇴심적설계、실험등공작。
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.