| 高通量研究堆堆芯热工水力分析程序THAS-PC4 |
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| 引用本文： | 郝老迷,李运文.高通量研究堆堆芯热工水力分析程序THAS-PC4[J].核科学与工程,1997(1). |
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| 作者姓名： | 郝老迷 李运文 |
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| 作者单位： | 中国原子能科学研究院 |
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| 摘 要： | 针对高通量研究堆的热工水力特点和设计准则开发了堆芯子通道分析微机程序ＴＨＡＳ－ＰＣ４。该程序能够计算稳态和瞬态工况下堆芯内冷却剂的流量、温度、密度和压力等参量的分布以及燃料元件的温度场。它还可以确定临界热流密度和偏离泡核沸腾比（ＤＮＢＲ），泡核沸腾开始时的壁面温度以及流动开始不稳定时的热流密度等，以评价反应堆的安全性。
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| 关 键 词： | 高通量研究堆 子通道分析 DNBR 泡核沸腾开始 流动不稳定性 |
THAS PC4: A THERMAL HYDRAULIC ANALYSIS CODE FOR HIGH FLUX RESEARCH REACTORS WITH PLATE TYPE FUEL ELEMENTS |
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| HAO LAOMI,LI YUNWEN.THAS PC4: A THERMAL HYDRAULIC ANALYSIS CODE FOR HIGH FLUX RESEARCH REACTORS WITH PLATE TYPE FUEL ELEMENTS[J].Chinese Journal of Nuclear Science and Engineering,1997(1). |
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| Authors: | HAO LAOMI LI YUNWEN |
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| Affiliation: | China Institute of Atomic Energy |
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| Abstract: | Based on the thermohydraulics and design criteria of high flux research reactors with plate-type fuel elements, the computer code THAS-PC4 has been developed to calculate the distributions of coolant flow, temperature, density and pressure in core, and the temperature field in fuel element. Then local CHF and DNBR, ONB temperature (T WONB ) and heat flux at onset of flow instability are determined to evaluate the reactor safety. |
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| Keywords: | high flux research reactor subchannel analysis DNBR onset of nucleate boiling flow instability |
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