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三环路压水堆压力容器上腔室交混矩阵数值研究 被引量:3

Numerical Analysis of RPV Upper Plenum Mixing Matrix in Three Loop PWRs
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摘要 使用STAR-CCM+软件对三环路压水堆压力容器上腔室流场进行了大规模、精细化三维数值模拟,并采用组分跟踪方法分别对157个燃料组件出口冷却剂流动进行计算,构造了一个具有3×157个元素的"上腔室交混矩阵",用该矩阵即可定量、精确地描述冷却剂从堆芯流出后,经上腔室内交混并再分配到各热管道的复杂流动过程。研究发现堆芯流出的冷却剂在压力容器上腔室内的交混是并不充分的,径向上不同位置燃料组件流出的冷却剂会在上腔室同热管道的接口区域存在明显的对应关系,而燃料组件径向功率分布的差异必然导致热管道中冷却剂热分层现象的产生。 A large-scale and refined three-dimensional numerical simulation of the upper plenum flow field of the pressure vessel of the three-loop pressurized water reactor is carried out by using the commercial CFD software STAR-CCM+ code. The coolant flow at the outlet of 157 fuel assemblies is calculated by the component tracking method. A mixing matrix of the upper plenum with 3×157 elements is constructed, which can be used to quantitatively and accurately describe the complex flow process of the coolant flowing out from the reactor core and mixing in the upper plenum and redistributing to the hot legs. It is found that the mixing of the coolant flowing from the core is not thorough and complete in the upper plenum of pressure vessel. The coolant flowing from fuel assembly at different positions in the radial direction is with obvious corresponding relationship in the interface area between the upper plenum and the hot legs, and the difference of the radial power distribution of fuel assembly will inevitably lead to the formation of the thermal stratification of the coolant in hot legs.
作者 宋磊 何向艳 程艳花 崔大伟 Song Lei;He Xiangyan;Cheng Yanhua;Cui Dawei(China Nuclear Power Technology Research Institute,Shenzhen,Guangdong,518026,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2020年第4期55-59,共5页 Nuclear Power Engineering
关键词 压水堆 压力容器上腔室 CFD 交混矩阵 数值模拟 PWR RPV upper plenum CFD Mixing matrix Numerical simulation
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  • 1汪晓林,朱丽冬,高际运.压水堆上腔室模拟体三维流场分析[J].核动力工程,1995,16(3):231-236. 被引量:4
  • 2朱丽冬,30万千瓦压水堆上腔室流场研究及其工程应用,1996年
  • 3邢宗文,流体力学基础,1992年
  • 4邢宗文,流体力学基础,1992年,228页
  • 5范静龙,朱丽兵,张明,等.300Mw压力堆核电站反应堆下腔室流场数值模拟[R].第十一届全国反应堆结构力学会议,2000:26-30.
  • 6张曙明,赵民富,李华奇,等.秦山二期反应堆堆芯流量分配数值分析[Z].中国核科学技术进展报告,2009.
  • 7于浩,翁羽.反应堆堆内构件上腔室流场初步分析研究[R].第十六届全国反应堆结构力学会议,2010:315-324.
  • 8Mahaffy J, Chung B, Dubois F, et al. Best practice guidelines for the use of CFD in nuclear reactor safety applications[R]. OECD, Nuclear Energy Agency, Technical Report, 2007.
  • 9Jeong J H, Han B S. Coolant flow field in a real geometry of PWR downcomer and lower plenum[J]. Annals of Nuclear Energy, 2008, 35:610-619.
  • 10Farajollahi H, Ghasemizad A, Khanbabaei B. CFD-calculation of fluid flow in a pressurized water reactor[J]. Journal of Sciences(Islamic Republic of Iran),2008, 19(3): 273-281.

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