scholarly journals NUMERICAL SIMULATION ON THERMAL DIFFUSION CONCERNING AIR-SEA HEAT EXCHANGE EFFECTS

1986 ◽  
Vol 1 (20) ◽  
pp. 183
Author(s):  
P.C. Chyen ◽  
C.S. Yang ◽  
I.L. Wang ◽  
H.H. Hwung

The numerical simulations on thermal diffusion always concentrated upon the raised temperature and temperature distributions after the heated water discharged from outlet into surrounding water, and the surrounding water temperature was assumed to be a constant. Actually, the water temperature on surface layer in shallow water area varies several centigrade degrees depended upon the weather conditions during a whole day. In order to obtain the absolute water temperature prepared for the ecological changes assessment and even provided for the operation basis of the cooling water system that air-sea heat exchange has to be considered in the numerical simulation of thermal discharges. For the practical application of this numerical simulation, the first nuclear power plant in Taiwan was taken as an example and simulated in this paper. And the results were presented in figures.

Author(s):  
Jin-hua Liu ◽  
Bin Gong ◽  
E Jang ◽  
Wei-gang Ma ◽  
Ju-hua Wen ◽  
...  

Based on the corrosion issues of component cooling water system (CCWs) in nuclear power plant (NPP), the corrosion inhibition properties and protection mechanism on copper and stainless steel was studied by using tests such as electrochemical method, immersion test and dynamic water simulation. Results show that the optimum inhibitor is the compound of tolyltriazole (TTA) and phosphate, which has an excellent corrosion inhibition efficiency on copper in either pure water or abnormal water. The inhibitor also elevated the pitting potential of stainless steel and contributed to the corrosion resistance.


Author(s):  
Bumpei Fujioka ◽  
Naoki Hirokawa ◽  
Daisuke Taniguchi

In the Fukushima Dai-ichi nuclear power station, Loss of Ultimate Heat Sink (LUHS) was caused by the great east japan earthquake and the subsequent tsunami [1]. It resulted in severe accident in three units. In that time, fuel damage in Spent Fuel Pool (SFP) were prevented by the various countermeasures such as makeup by pump truck and recovery of injection systems /cooling water system. In the past, Probabilistic Safety Assessment (PSA) has been developed with a focus on the reactor. After the accident, it has been acknowledged that SFP PSA is important to enhance the plant safety. In this study, probabilistic assessment is performed to suggest countermeasures for LUHS to SFP.


1976 ◽  
Vol 1 (15) ◽  
pp. 175 ◽  
Author(s):  
Masanobu Kato ◽  
Akira Wang

In formation processes of the region of water temperature rise caused by the cooling water discharge from thermal and nuclear power stations located on the site facing the ocean, flow of discharged cooling water itself, current and turbulence existing in the sea region play an important role. Their motions are predominant in the horizontal direction in the sea region. The horizontal scale of thermal extent is, therefore, extremely larger than the vertical scale of thermal extent. Therefore, whenever the diffusion experiments of discharged warm water in the far field are conducted by hydraulic model method, the model which has a difference in the geometrical reduced rate between the horizontal and vertical directions, what is called, the distorted model must be used, so that the effects of the viscosity and the surface tension on the experimental model can be avoided. In such a model, the horizontal scale is determined by the relation between the size of the experimental water basin and the surface area of the sea region to be reproduced. But, there is no clear method of choosing the vertical scale, though there are some suggestions about it. For example, the similarity of the 4/3 power law of the diffusion coefficient gives a relation between the vertical scale and the horizontal scale of the hydraulic model. On the other hand, the similarity of the surface heat exchange coefficient gives another relation between the vertical scale and the horizontal scale of hydraulic model if the surface heat exchange coefficients of hydraulic model and prototype are not same. Therefore, it is better to give some allowance in the determination of the vertical scale of the hydraulic model within the range where the reproducibility of the diffusion phenomena can be conserved.


2020 ◽  
Vol 329 ◽  
pp. 03049
Author(s):  
Aleksey Babushkin ◽  
Sergey Skubienko ◽  
Ludmila Kinash

In this study, the influence of the cooling water temperature on the thermal efficiency of a conceptual pressurized-water reactor nuclear- power plant is studied. The change in the cooling water temperature can be experienced due to the seasonal changes in climatic conditions at plant site. The article presents the results of technical and economic parameters study of nuclear power unit’s operation under increased vacuum value. Investigated seasonal variations of cooling water temperature, cooling water temperature influence on the vacuum temperature in the turbine condenser, and changing the basic technical and economic performance of nuclear power station. The mathematical model of calculation the nuclear power plant operation for a 1000 MW power unit was developed.


Author(s):  
I Wayan Nurjaya ◽  
Heron Surbakti

Thermal dispersion model based on the hydrodynamics model was applied on PLTGU Cilegon (electric power industry based on gas and steam) at the coast of Margasari, Pulo Ampel District, Serang-Banten. This PLTGU used around 60.000 mP3P/hour of seawater as cooling water system. Therefore, it produced water with high temperature of about 5 PoPC higher than the sourounding of seawater temperature. This high water temperature was flowed out into the coastal waters. This study tried to predict their distribution according to southeast and northeast monsoon. Model verification was conducted both to hydrodynamics component (tide and current) and water temperature. The verification results show good enough patterns between the model results and field measurement.Key words: Bay of Banten, cooling water system, thermal dispersion, hydrodynamics model


1970 ◽  
Vol 92 (2) ◽  
pp. 150-156 ◽  
Author(s):  
F. J. Jeffers ◽  
J. C. Geyer ◽  
L. C. Neale

A coordinated program is described for developing information needed for designing a condenser cooling water system for a nuclear power plant located on a large estuary to meet State water quality standards and minimize any adverse effects on aquatic life. The paper discusses estuarine conditions pertinent to the design of the intake and discharge structures, the heat assimilative capacity of the estuary, application of the momentum jet theory to the condenser cooling water discharges, and hydraulic model investigations to determine mixing and dispersion patterns.


Author(s):  
Jianfeng Shi ◽  
Dongsheng Hou ◽  
Weican Guo ◽  
Yaoda Zhou ◽  
Xia Chen ◽  
...  

Polyethylene (PE) pipe has many advantages such as good flexibility, corrosion resistance and long service life. It has been introduced into nuclear power plants for transportation of cooling water both in U.S. and Europe. Recently, one Chinese nuclear power plant in Zhejiang Province also introduced four polyethylene pipelines in essential cooling water system with operating pressure of 0.6MPa and operating temperature of no more than 60°C. The PE pipes used in this nuclear power plant are DN762 SDR9 (30in OD, 3.3in wall), which are much larger and thicker than traditional natural gas PE pipe. As the pipe wall is so thick that the ultrasonic phased array instrument used in inspection of PE pipe with diameter less than 400mm has been improved. Results of field inspection in the Sanmen nuclear plant are reported, and the presented ultrasonic inspection technique proves to be effective for high density polyethylene (HDPE) pipe of large size in nuclear power plant.


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