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Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors

热的自然传送对流特征的数字调查为熔融的盐反应堆的凉下来管子的被动剩余热移动系统

作     者:Cheng-Long Wang Hao Qin Da-Lin Zhang Wen-Xi Tian Guang-Hui Su Sui-Zheng Qiu Cheng-Long Wang;Hao Qin;Da-Lin Zhang;Wen-Xi Tian;Guang-Hui Su;Sui-Zheng Qiu

作者机构:Department of Nuclear Science and TechnologyXi’an Jiaotong UniversityXi’an 710049China Shaanxi Key Laboratory of Advanced Nuclear Energy and TechnologyXi’an Jiaotong UniversityXi’an 710049China State Key Laboratory of Multiphase Flow in Power EngineeringXi’an Jiaotong UniversityXi’an 710049China 

出 版 物:《Nuclear Science and Techniques》 (核技术(英文))

年 卷 期:2020年第31卷第7期

页      面:25-33页

核心收录:

学科分类:082703[工学-核技术及应用] 08[工学] 0827[工学-核科学与技术] 

基  金:supported by the National Key R&D Program of China(No.2019YFB1901100) the National Natural Science Foundation of China(No.11705138) the China National Postdoctoral Program for Innovative Talents(No.BX201600124) 

主  题:passive characteristics pipes 

摘      要:The limited availability of studies on the natural convection heat transfer characteristics of fluoride salt has hindered progress in the design of passive residual heat removal systems(PRHRS)for molten salt *** paper presents results from a numerical investigation of natural convection heat transfer characteristics of fluoride salt and heat pipes in the drain tank of a *** results are compared with experimental data,demonstrating the accuracy of the calculation *** distribution of fluoride salt and heat transfer characteristics are obtained and *** radial temperature of liquid fluoride salt in the drain tank shows a uniform distribution,while temperatures increase with increase in axial height from the bottom to the top of the drain *** addition,natural convection intensity increases with increase in height of the heat pipes in the *** between heat pipes has no obvious effect on the natural convection heat transfer *** study will contribute to the design of passive heat removal systems for advanced nuclear reactors.

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