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作 者:苏阳 李晓伟 吴莘馨 SU Yang;LI Xiaowei;WU Xinxin(Key Laboratory of Advanced Reactor Engineering and Safety,Ministry of Education,Collaborative Innovation Center for Advanced Nuclear Energy Technology,Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China)
机构地区:[1]清华大学核能与新能源技术研究院,先进核能技术协同创新中心,先进反应堆工程与安全教育部重点实验室,北京100084
出 处:《原子能科学技术》2022年第12期2747-2756,共10页Atomic Energy Science and Technology
基 金:国家重点研究发展项目(2020YFB1901600);国家自然科学基金(51576103);国家科技重大专项(ZX06901)。
摘 要:两相流稳定性是直流蒸发器重点关注的热工水力学问题。本文在已有频域理论模型的基础上,考虑到单相段和两相段管径的不同,建立了含流通面积改变的两相流稳定性频域理论模型。模型预测结果与HTR-10和HTR-PM螺旋管式直流蒸发器工程验证试验结果吻合较好。然后用所建立的模型及方法对比分析了倾斜直管、不同螺旋直径螺旋管及变管径直流蒸发器的两相流稳定性。对于大入口节流系统,当其他条件相同时,由于直管阻力系数小于螺旋管,所以具有相同倾角的倾斜直管比螺旋管稳定。对于大入口节流系统,增加螺旋直径后阻力系数降低,所以增加螺旋直径有利于系统的稳定性,但稳定性效果增加有限。相比于等管径设计,采用单相段内径小于两相段和过热段内径的设计可稍微提高系统的稳定性。As the fourth generation nuclear power technology, high temperature gas-cooled reactor(HTGR) has good prospects due to its inherent safety and high temperature. Two-phase flow stability is one of the most important thermal hydraulic issues for steam generators. For the steam generator of HTR-PM(high temperature gas-cooled reactor-pebble module), the size of the inner tube diameter is uniform. While for steam generator of HTR-10(10 MW high temperature gas-cooled reactor), the inner tube diameter of single-phase preheating region is smaller than that of two-phase and superheated regions. A model with variable tube diameter will be established to predict the stability boundary of HTR-PM and HTR-10 steam generators. The heat transfer tube of the steam generator is divided into three regions, and they are single-phase preheating region, two-phase flow region and superheated region. Based on the existing frequency domain theoretical model, a new frequency domain theoretical model with different inner tube diameters for the single-phase preheating region and two-phase region was established for analyzing two-phase flow stability. System stability was determined by the Nyquist curve of the open transfer function. The prediction of the new proposed model is in good agreement with the engineering test results of HTR-10(variable tube diameter) and HTR-PM(uniform tube diameter) once through steam generators. Then, the effects of friction factor difference between helical tube and inclined straight tube, the effects of helical diameter difference, and the effects of different tube diameters for single-phase preheating and two-phase regions on two-phase flow stability were analyzed. For systems with high inlet resistance coefficients, when other conditions are the same, the friction factor of an inclined straight tube is smaller than that of a helical tube, so the system with an inclined straight tube(the inclined angle is the same as the helical angle of the helical tube) is more stable than the system with a helical tube. Wh
关 键 词:螺旋管式直流蒸发器 频域理论模型 螺旋直径 管径
分 类 号:TL333[核科学技术—核技术及应用]
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