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多个两流体程序耦合的核电站系统热工水力建模及仿真研究 被引量:3

Study on thermal-hydraulic modeling and simulation of nuclear power plant systems based on multiple coupling of two-fluid code
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摘要 为了增加核电站工程模拟器的仿真范围和精度,介绍了基于多个两流体程序耦合的热工水力系统建模方法,并利用RCV与主系统的耦合模型对其准确性进行了验证。基于此,建立了比较全面的核电站系统热工水力模型,并将其在工程模拟器上进行了应用。结果表明,基于多个两流体程序耦合的模型扩展,在保证精度的基础上,增加了模拟器的计算范围,而且可以解决单一模型中节点数量有限、模型庞大导致计算速度较慢、调试困难等问题,从而为提高工程模拟器的性能提供了一个方便可行的方法。 In order to increase the simulation scope and accuracy of nuclear power plant simulator, the modeling method of thermal-hydraulic systems based on multiple coupling of two-fluid code is described, and the accuracy of this method is verified by using RCV model coupled with the main system. Based on this, more comprehensive thermal-hydraulic model of nuclear power plant systems is established, and the application of it to engineering simulator is performed. The results show that model extension based on multiple coupling of two-fluid code, on the basis of accuracy, has expended calculation scope of the simulator, and can solve the problems of low calculation speed and difficult debugging and so on, which are led by the limited number of nodes in a single model. Therefore it provides a convenient and feasible method to improve the performance of the engineering simulator.
出处 《核科学与工程》 CSCD 北大核心 2012年第2期186-192,共7页 Nuclear Science and Engineering
关键词 两流体程序 热工水力系统 耦合 仿真 two-fluid code thermal-hydraulic system coupling simulation
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  • 1The RELAP5 Code Development Team. RELAP5/MOD3 Code Manual[M]. USA: Idaho National Engineering Laboratory, 1995. 被引量:1
  • 2Postel J. Internet Protocol[M]. RFC 791(Standard), September 1981. 被引量:1
  • 3Postel J. Transmission Control Protocol[M]. RFC 793(Standard), September 1981. 被引量:1
  • 4Geist, A. PVM3 User's Guide and Reference, ORNL:TM-12187 [M]. Oak Ridge National Laboratory, 1994. 被引量:1
  • 5Jeong, J-J. Development of a Multi-Dimensional Thermal-Hydraulic System Code, MARS 1.3.1 [J]. Annals of Nuclear Energy, 1999, 26:1611~1642. 被引量:1
  • 6Smith, K A. Coupled RELAP5 and CONTAIN Accident Analysis Using PVM[J]. Nuclear Safety, 1995, 36 (1),94~108. 被引量:1

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