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-Reference-Cited by-同舟云学术

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

Published:2010-07 Issue:7 Volume:57 Page:579-587
ISSN:0040-6015
Container-title:Thermal Engineering
language:en
Short-container-title:Therm. Eng.

Author:

Tomarov G. V.,Shipkov A. A.

Publisher

Pleiades Publishing Ltd

Subject

Energy Engineering and Power Technology,Nuclear Energy and Engineering

Link

http://link.springer.com/content/pdf/10.1134/S0040601510070086.pdf

Reference11 articles.

1. H. G. Heitmann and W. Kasner, “Erosion-Corrosion in Water/Steam Cycles — Causes and Corrective Measures,” VGB. Kraftwerkstechnik 62(3), 211–219 (1982).

2. T. Kh. Margulova and O. I. Martynova, Water Chemistries of Thermal and Nuclear Power Stations (Vysshaya Shkola, Moscow, 1987) [in Russian].

3. O. A. Povarov, G. V. Tomarov, E. V. Velichko, et al., Erosion-Corrosion Wear of the Metal of Elements Used in Turbine Units of Thermal and Nuclear Power Stations: A Review (TsNIITEItyazhmash, Moscow, 1991) [in Russian].

4. O. A. Povarov, G. V. Tomarov, and V. F. Chertushkin, “The Flow of Liquid Films at Increased Values of Density and Velocity of Wet Steam,” Izv. Ross. Akad. Nauk, Energetika, No. 3, 166–173 (2002).

5. O. I. Martynova, O. A. Povarov, G. V. Tomarov, and A. F. Gontarenko, “Inhibiting Erosion-Corrosion of the Metals of Turbine Units in One- and Two-Phase Flows,” Tyazh. Mashinostr., No. 8, 18–21 (1990).

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Flow-Accelerated Corrosion Wear of Power-Generating Equipment: Investigations, Prediction, and Prevention: 2. Prediction and Prevention of General and Local Flow-Accelerated Corrosion;Thermal Engineering;2018-07-18