| 两相流稳定裕度 |
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| 引用本文： | 张佑杰,博金海,吴少融,王飞. 两相流稳定裕度[J]. 清华大学学报(自然科学版), 1995, 0(6) |
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| 作者姓名： | 张佑杰 博金海 吴少融 王飞 |
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| 作者单位： | 清华大学核能技术设计研究院 |
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| 摘 要： | 进行了用相关分析系统辨识方法判别两相流稳定裕度的实验研究。由于采用了该实验方法使两相流动稳定性实验研究方法建立在控制理论基础上，可以在系统正常运行工况下判定两相流稳定裕度及其动态特性，对核供热堆的两相流稳定性预报有实用价值，实验是在核供热堆热工水力学模拟实验系统ＨＲＴＬ－５上进行的，实验结果对两相流动态数学模型的建立与验证提供基础数据。
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| 关 键 词： | 核供热堆 系统识别 两相流 稳定裕度 |
Stability margin of two phase flow |
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| Zhang Youjie, Bo Jinhai, Wu Shaorong, Wang Fei Institute of Nuclear Energy Technology,Tsinghua University. Stability margin of two phase flow[J]. Journal of Tsinghua University(Science and Technology), 1995, 0(6) |
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| Authors: | Zhang Youjie Bo Jinhai Wu Shaorong Wang Fei Institute of Nuclear Energy Technology Tsinghua University |
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| Abstract: | An experimental study on distinguishing stability margin of two phase flow by means of system correlation identification is described. The experiment method is established on the basis of control theory by using system identification. The instability margin and dynamic character of two phase flow system can be distinguished in unchanged working condition, it is useful to forecast instability of the nuclear heating reactor (NHR) system. The experiment was carried out on the thermohydraulic test system HRTL-5. Basic data for mathematics model establishing and verifying of two phase flow were obtained. |
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| Keywords: | nuclear heating reactors (NHR ) system identifications two phase flow stability margin |
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