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作 者:胡高杰[1] 于雷[1] 郝建立[1] 储玺 HU Gao-jie YU Lei HAO Jian-li CHU Xi(Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan 430033, Chin)
机构地区:[1]海军工程大学核能科学与工程系,湖北武汉430033
出 处:《原子能科学技术》2017年第1期67-72,共6页Atomic Energy Science and Technology
基 金:国家自然科学基金资助项目(11502298);核反应堆系统设计技术国家重点实验室基金资助项目(HT-ZDSY-02-2015004);核安全与仿真技术国防重点学科实验室基金资助项目(2015A041)
摘 要:针对立式倒U型管蒸汽发生器传热管内出现的倒流现象,基于RELAP5/MOD3.3程序,采用新的控制体划分方案对蒸汽发生器实验段进行建模,模拟实验回路中发生的倒流现象。通过与实验数据进行对比分析,验证建模方案的正确性。在此基础上,分析倒流现象对蒸汽发生器实验段流动传热的影响。结果表明:倒流现象发生在较短管内,对于单个U型管,倒流管的流量高于正流管。倒流发生后,系统进入相对稳定状态,但蒸汽发生器实验段的换热功率和进出口腔室负压降绝对值显著降低。For the reverse flow phenomenon in the vertically inverted U-tube steam generators,a new node partition scheme was used to model the steam generator test section based on the system analysis code RELAP5/MOD3.3.The reverse flow phenomenon in the process of experiment was simulated in this paper.Compared with the experimental data,the correctness of the new scheme developed in this paper was verified.The results show that the reverse flow phenomenon occurs in the shorter U-tubes.For single U-tube,the mass flow rate of reverse flow is generally greater than that of normal flow U-tube.When the reverse flow occurs,the system will get into a relatively stable state.However,the negative pressure drop between the inlet and outlet plenums and the heat exchange of test section reduce significantly.
分 类 号:TL333[核科学技术—核技术及应用]
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