The diagram of pH values in the liquid and steam phases during a change in the aggregate state of H2O in the process circuit of nuclear and thermal power stations

被引:0
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作者
Tomarov G.V. [1 ]
Shipkov A.A. [1 ]
机构
[1] ZAO Geoterm-EM, Moscow 111020
关键词
Steam; Liquid Film; VVER Reactor; Secondary Coolant Circuit; Interphase Distribution;
D O I
10.1134/S0040601510070086
中图分类号
学科分类号
摘要
We present data on the effect the pH value of liquid film has on the rate of erosion-corrosion processes in the metal of thermal and nuclear power station elements operating with two-phase flows. We also suggest a calculation diagram and an engineering procedure for determining the pH value of liquid phase in the wet-steam paths of power units depending on the concentration of corrective additions, steam wetness ratio, and temperature. © 2010 Pleiades Publishing, Ltd.
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页码:579 / 587
页数:8
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