scholarly journals Effect of Dissolved Oxygen on Aluminum Corrosion in Simulated Cooling Water for HVDC Systems at 50 °C

2021 ◽  
pp. ArticleID:210529
Author(s):  
Liangshou Hao ◽  
CORROSION ◽  
10.5006/2695 ◽  
2017 ◽  
Vol 74 (5) ◽  
pp. 577-587 ◽  
Author(s):  
Yuichi Fukaya ◽  
Toshifumi Hirasaki ◽  
Katsuhiko Kumagai ◽  
Teruhisa Tatsuoka ◽  
Kenro Takamori ◽  
...  

This synopsis describes corrosion issues and mitigation activities shortly after the Fukushima Daiichi Nuclear Power Station accident. An earthquake of magnitude 9.0 occurred on March 11, 2011; the subsequent tsunami removed the cooling capacity of fuels in both the reactors and spent fuel pools (SFPs). Seawater was temporarily used for emergency fuel cooling, which induced various corrosion issues. Just after the accident, the temperatures within the reactors of Units 1 to 3 increased to several hundred degrees Celsius and the water quality of the cooling water seems to have become similar to that of concentrated seawater. To stabilize the fuel cooling, corrosion mitigation actions were required for mainly carbon steel components. The following corrosion mitigation measures were applied to the reactors: (a) temperature decreases, (b) dissolved oxygen removal from feedwater via deaeration, (c) dissolved oxygen removal from cooling water in the reactors via nitrogen gas injection, (d) salt removal from cooling water, and (e) sterilization of feedwater by hydrazine addition. The temperatures of SFP water in Units 1 to 4 were between 47°C and 93°C just after the accident. The maximum chloride ion concentration was approximately 2,000 ppm and the pH was in the range from 7.5 to 11.2. The mitigation of localized corrosion of the stainless steel pool liners and alkaline corrosion of the aluminum fuel racks was the top priority. In addition to (a), (b), and (d) listed above, (f) dissolved oxygen removal and sterilization by hydrazine addition and (g) pH control were applied to the SFPs. In the six years since the accident, no major corrosion problems have yet arisen. However, continued efforts to increase plant stability are underway for the long-term goal of decommissioning.


2022 ◽  
Vol 2150 (1) ◽  
pp. 012010
Author(s):  
A D Vodeniktov ◽  
N D Chichirova

Abstract Study presents the results of the steam surface KCS-200-2 reconstruction. In order to maintain the dissolved oxygen concentration, according to the Code of Operation for Power Plants, the steam sparger was installed in condenser hotwell. Despite the abnormal air leakage level, reducing of dissolved oxygen concentration was reached. The dissolved oxygen concentration reduced, on average, by 2 times. As it was expected, in the cases of low inlet cooling water temperature, the final oxygen concentration did not reach the normal level. In last 3 tests the dissolved oxygen concentration was reduced to 19 mg /l. The results show a possibility of described reconstruction experience.


Author(s):  
A.D. Vodeniktov ◽  
◽  
N.D. Chihirova ◽  

In this paper, the results of the steam turbine condenser tests showing the dependence of the dissolved oxygen concentration and the water cooling temperature are presented. The steam surface condenser with the water cooling system is considered as the first stage of deaeration in the feedwater system of a steam turbine. The aim of this work is trying to investigate and describe the influence of regime factors on the deaeration effect of the steam surface condenser. Regimes with the nominal flow of the steam in the surface condenser were chosen for the estimation. The tests were continuing for 6 months in the range of the temperature of cooling water from 1 to 25 оС. The vacuum system of the steam turbine had a high level of air leakages that decreasing the efficiency of the feedwater dearation. The results show the negative correlation between dissolved oxygen in feedwater and the cooling water temperature. The surge of the concentration of dissolved oxygen was found in the water temperature about 11оС.


Author(s):  
W. C. Bigelow ◽  
F. B. Drogosz ◽  
S. Nitschke

High vacuum systems with oil diffusion pumps usually have a pressure switch to protect against Insufficient cooling water; however, If left unattended for long periods of time, failure of the mechanical fore pump can occur with equally serious results. The device shown schematically in Fig. 1 has been found to give effective protection against both these failures, yet it is inexpensive and relatively simple to build and operate.With this system, pressure in the fore pump line is measured by thermocouple vacuum gage TVG (CVC G.TC-004) whose output is monitored by meter relay MRy (Weston 1092 Sensitrol) which is set to close if the pressure rises above about 0.2 torr. This energizes control relay CRy (Potter & Brumfield KA5Y 120VAC SPDT) cutting off power to solenoid-operated fore line valve Vf (Cenco 94280-4 Norm. Closed) which closes to prevent further leakage of air into the diffusion pump


Author(s):  
P. Ackers ◽  
J.D. Pitt ◽  
G. Thompson ◽  
K.G. Rippin
Keyword(s):  

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