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作 者:焦宏[1] 田文喜[1] 秋穗正[1] 苏光辉[1]
机构地区:[1]西安交通大学动力工程多相流国家重点实验室核科学与技术系,陕西西安710049
出 处:《原子能科学技术》2011年第4期421-425,共5页Atomic Energy Science and Technology
基 金:科技部ITER计划专项课题资助项目(2009GB109001)
摘 要:利用CFX程序对聚变驱动次临界堆嬗变包层第一壁在水冷条件下的热工水力特性进行数值模拟和分析。计算选用PWR典型工况下的水,取嬗变包层第一壁的局部模型,考虑了流固热耦合,重点计算分析了在不同壁面热流密度和冷却剂流速条件下冷却剂温度、压降及结构材料最高温度的分布。计算结果显示,当水的入口流速为1~5m/s时,结构材料的最高温度较使用典型工况下的氦气作冷却剂时低16~91K,同时结构材料最大温差降低了12.2%~49.5%。结果表明:水可较好地满足稳态工况下第一壁的换热要求。The CFX software was used for the simulation and analysis of thermal-hydraulic characteristics of the water-cooled first wall of dual-cooled waste transmutation blanket(DWTB) in fusion driven subcritical system(FDS).Water in the typical operational condition of PWR was used as the coolant in this calculation.The calculation was carried out on a partial model of the first wall,in which coupling of heat transfers between solid and fluid was considered.Focus is placed on the temperature distribution of first wall structure,temperature distribution and pressure drop of the coolant at different wall heat fluxes and coolant flow rate.The calculation results show that when the inlet speed of water ranges from 1 m/s to 5 m/s,maximum temperature of the structure is 16 K to 91 K lower than when the structure is cooled by helium under typical operational conditions.Difference between maximum and minimum temperature of the structure is also 12.2% to 49.5% lower.The results show that the water-cooled system can meet the thermal-hydraulic requirements of the first wall under steady-state conditions.
分 类 号:TL33[核科学技术—核技术及应用]
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