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多孔介质通道内两相流动特性数值研究 被引量:3

CFD Study on Two-Phase Flow Characteristics in Pebble-Bed Porous Media Channel
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摘要 针对球床式水冷堆堆芯单根燃料组件,采用FLUENT软件中的多孔介质模型对燃料组件内冷却剂的热工水力特性进行了数值计算。分析了组件内冷却剂从单相水到过热蒸汽的变化过程,并对不同工况下的计算结果进行了分析。计算得到了多种稳态运行模式下组件内空泡份额、压力、汽相温度、汽相流速等参数的变化规律以及系统参数对热工特性的影响。结果表明,由于多孔介质的存在,组件内的阻力比轻水反应堆更大,堆芯压降也相应增大。正常工况下,堆芯冷却剂温升较大,冷却剂跨越液相区、相变区以及单相蒸汽区,各区流动换热特性差异大。当运行模式发生改变时,与轻水反应堆相比,球床式水冷堆堆芯的流动换热参数值变化更大,但无论是稳态工况还是瞬变工况下的冷却剂温度均满足安全准则。 For the single fuel assembly of the new conceptual pebble bed water cooled reactor(PBWR),the thermal-hydraulic characteristics of the coolant in the fuel assembly were studied based on the porous media model of FLUENT.The phase change process from single-phase water to superheated steam in the fuel components was analyzed at different working conditions.The void fraction,pressure,temperature and gas velocity distributions had been calculated and analyzed under steady state operating modes such as the full power,half power,and low flow rate.The result shows that due to the existence of porous media,the resistance in the fuel assembly is greater than that in the light water reactor(LWR),and the pressure drop in the core increases accordingly.The coolant temperature rise is relatively large under normal operating conditions,and the coolant crosses the liquid phase region,phase change region and single-phase steam region,and the flow and heat transfer characteristics of each region are quite different.When the operation mode is changed,the flow and heat transfer parameters of the PBWR vary more than that of LWR,and the coolant temperature can meet the safety criteria in both steady-state and transient conditions.
作者 李华 张友佳 李云 秋穗正 张林 黄春兰 彭园 Li Hua;Zhang Youjia;Li Yun;Qiu Suizheng;Zhang Lin;Huang Chunlan;Peng Yuan(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu,610213,China;Department of Nuclear Science and Technology,Xi'an Jiaotong University,Xi'an,710049,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2020年第S02期59-63,共5页 Nuclear Power Engineering
关键词 多孔介质 球床式水冷堆 两相流动 数值计算 Porous media Pebble bed water cooled reactor Two-phase flow characteristics CFD
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