LSTF被动余热去除系统的传热建模

IF 0.6 4区 工程技术 Q4 Engineering Nuclear Engineering International Pub Date : 1997-11-16 DOI:10.1115/imece1997-0612
G. McCreery, C. Kullberg, R. Schultz, T. Yonomoto, Y. Anoda
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引用次数: 0

摘要

在模拟的冷却剂损失事故中,ROSA设施中运行的被动余热去除(PRHR)系统的模型数据与使用一维稳态计算机模型的传热计算进行了比较。计算结果与实际数据相当吻合。PRHR由一个“C”形管束淹没在一个装满水的大水箱中组成。计算结果表明,在换热器进口附近发生过冷核沸腾。在管的水平和垂直方向上,沸腾区之后是湍流区,然后是层流自然对流区。过渡沸腾,间歇性地出现附在管道上的蒸汽块,在较高的传热试验中可能发生在入口附近,但对整个传热过程没有显著影响。
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Heat Transfer Modeling of the LSTF Passive Residual Heat Removal System
Data from a model Passive Residual Heat Removal (PRHR) system operated in the ROSA facility during simulated loss-of-coolant accidents were compared with heat transfer calculations using a one-dimensional steady-state computer model. The calculations agree reasonably well with the data. The PRHR consists of a “C” shaped tube bundle submerged in a large tank filled with water. The calculations show that subcooled nucleate boiling occurred near the heat exchanger inlet. The boiling region was followed by turbulent and then laminar natural convection regions for horizontal and vertical the tubes. Transition boiling, with intermittently occuring patches of steam attached to the tubes, may have occurred near the inlet for the higher heat transfer tests, but did not significantly affect the overall heat transfer process.
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来源期刊
Nuclear Engineering International
Nuclear Engineering International 工程技术-核科学技术
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6-12 weeks
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