期刊文献+

电站压水堆堆芯水力模拟技术 被引量:5

CORE HYDRXULIC MODELING OFPOWER STATION PWR
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摘要 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──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2x2棒束模拟原型17x17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600MWe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 as sembly-by-assembly modeling is put into practice,which makes it possible that the data of flow rate distribution factors at the core inlet havecorresponding relationship. This paper presents the common theory and method of powerstation PWR core hydraulic 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 the country. A 2×2rod bundle is developed to simulate the 17×17 rod bundle of prototype. For the purposeof 600MWe reactor hydraulic simulation test and core modeling, a turbine especially madeand an electrode that are located inside the model assemble are used to measure flow ratedistribution and flow mixing factors in the lower plenum respectively.
出处 《工程热物理学报》 EI CAS CSCD 北大核心 2000年第1期50-53,共4页 Journal of Engineering Thermophysics
基金 国家"八.五"攻关基金!85-213-01-01
关键词 核电站 压水堆 堆芯 水力模拟 power station PWR open lattice model fuel assembly
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参考文献1

  • 1汪利民,中国核动力研究设计院内部报告,1997年

同被引文献38

  • 1杨来生,宗桂芳,胡俊.秦山核电二期工程反应堆水力模拟实验研究[J].核动力工程,2003,24(z1):208-211. 被引量:15
  • 2杨来生,宗桂芳,胡俊.秦山核电二期工程反应堆水力模拟实验模型的简化[J].核动力工程,2003,24(z1):212-215. 被引量:3
  • 3田文喜,秋穗正,郭赟,苏光辉,贾斗南,刘天才,张建伟.中国先进研究堆稳态热工水力计算程序开发[J].原子能科学技术,2006,40(1):51-56. 被引量:11
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