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作 者:王聪 张巍 李净松[1,2] 乔鹏瑞 施慧烈 Wang Cong;Zhang Wei;Li Jingsong;Qiao Pengrui;Shi Huilie(China Nuclear Power Operation Technology Corporation,Wuhan,430074,China;Research Institute of Nuclear Power Operation,Wuhan,430074,China;China Institute of Atomic Energy,Beijing,102413,China)
机构地区:[1]中核武汉核电运行技术股份有限公司,武汉430074 [2]核动力运行研究所,武汉430074 [3]中国原子能科学研究院,北京102413
出 处:《核动力工程》2021年第4期171-175,共5页Nuclear Power Engineering
基 金:快堆产业联盟创新基金(2019-kdlm-cxjj-003);中核集团青年英才项目(CNPO-K200556)。
摘 要:铅冷快堆(LFR)采用一体化堆芯设计方案,其中的直流蒸汽发生器(OTSG)多采用螺旋管式结构以使整体结构小型紧凑。为研究LFR中螺旋管式OTSG壳侧铅铋冷却剂的流动传热特性,利用FLUENT软件,采用一种分区段计算方法,通过管壁热流密度拟合公式对螺旋管式OTSG壳侧进行了三维数值模拟。最终验证了该分段计算方法的正确性,分析了OTSG壳侧铅铋冷却剂的流动传热特性,获得了其速度、温度以及压力场的计算数据,为下一步OTSG流致振动分析和高温应力计算提供了依据。The lead based fast reactors often use integrated core design scheme,due to its compact structure,and the helical coil tube type once-through steam generators(OTSG)have been utilized in various reactors.In order to study the flow and heat transfer characteristics of the lead bismuth eutectic based coolant in the shell side of the helical coil tube OTSG in lead based fast reactors,a section-by-section solution method is adopted,and the wall heat flux fitting formula is used to simulate the flow field of shell side,with the help of FLUENT software.Finally,the correctness of the section-by-section solution method is verified,the flow and heat transfer characteristics of the shell side are analyzed,and the calculation data of velocity,temperature and pressure field are obtained.Its results lay a foundation for the next step of steam generator flow induced vibration analysis and high temperature stress calculation.
关 键 词:螺旋管 直流蒸汽发生器(OTSG) 数值模拟
分 类 号:TL331[核科学技术—核技术及应用]
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