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机构地区:[1]中国原子能科学研究院
出 处:《核科学与工程》2001年第3期252-259,276,共9页Nuclear Science and Engineering
摘 要:在单根U形管内进行蒸汽冷凝回流实验 ,研究冷凝回流的流动及阻液现象。U形管内径为 2 0mm ,总高度为 4 1m和 7 0m两种。主要实验参数范围为 :系统压力 0 1~ 6.0MPa ,蒸汽质量流速 4~ 4 5kg/ (m2 ·s) ,二次侧进口冷却水温度 2 0~ 1 96℃。给出了不同压力下冷凝回流阻液起始点无因次汽相折算速度jg ,并与典型的现有阻液计算关系式和分析模型进行了比较。实验结果与Wallis关系式 ,j 1/ 2g+j 1/ 2f =C(C =0 .8~ 0 .9) ,Faghri关系式 ,Kg1/ 2 +Kf1/ 2 =3.2tanhD 1/ 4。Reflux condensation was studied in single inverted U tubes( D =20 mm, L =4.1 m and 7.0 m) under the pressure range of 0.1~6.0 MPa,steam mass flow rate of 4~45 kg/(m 2·s) and inlet cooling water temperature of 20~196 ℃. Flow patterns were examined by measuring the pressure drop of the upflow and downflow of the U tube. The values of the non dimensional steam superficial velocity, j * g, for the onset of flooding at the U tube inlet were calculated from the measurements, and are well predicted by the Wallis correlation, j *1/2 g+ mj *1/2 f= C(m=1.0,C=0.8~0.9 ), Faghri correlation, K g 1/2 + K f 1/2 =3.2 tanh( D *1/4 ), and the authors' analytical model which was proposed based on the mass,momentum and energy conservation equations of condensing separated flow, and the envelope theories for obtaining the maximum possible operating line in a countercurrent flow.
关 键 词:压水堆 失水事故 冷凝回流 阻液 折算速度 U形管 蒸汽
分 类 号:TL421.1[核科学技术—核技术及应用] TL364.4
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