scholarly journals THERMAL DISCHARGES: PROTOTYPE vs. HYDRAULIC MODEL

1976 ◽  
Vol 1 (15) ◽  
pp. 173
Author(s):  
Gary C. Parker ◽  
C.S. Fang ◽  
Albert Y. Kuo
Keyword(s):  
Nuclear Power ◽  
Water Discharge ◽  
Cooling Water ◽  
Hydraulic Model ◽  
Physical Parameters ◽  
Thermal Discharge ◽  
James River ◽  
Model Experiments ◽  
Model Predictions ◽  
Physical Effects

Data on physical parameters in the James River around the condenser cooling water discharge of the Surry Nuclear Power Plant, taken prior to and during plant operation, were analyzed to determine the physical effects of the thermal discharge on the area and to compare the prototype distribution of excess temperature to predictions based on hydraulic model experiments. The results of this investigation indicated that the increase in water temperatures due to the thermal discharge did not represent a significant alteration of the physical environment outside the mixing zone. The thermal discharge experienced turbulent mixing and entrainment near the outfall and temperatures decreased rapidly in this region. Field data on temperature distributions around the discharge, when compared to predictions based on hydraulic model experiments, indicate that the model predictions were conservative.

scholarly journals ADAPTABILITY OF PREDICTION METHOD OF HYDRAULIC MODEL EXPERIMENT FOR THERMAL DIFFUSION

1976 ◽  
Vol 1 (15) ◽  
pp. 175 ◽  
Author(s):  
Masanobu Kato ◽  
Akira Wang
Keyword(s):  
Heat Exchange ◽  
Nuclear Power ◽  
Water Discharge ◽  
Cooling Water ◽  
Prediction Method ◽  
Hydraulic Model ◽  
Surface Heat ◽  
Horizontal Scale ◽  
Vertical Scale ◽  
Surface Heat Exchange

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.

Research on the Law of Thermal Effect of Floating Nuclear Power Plants Thermal Discharge

2015 ◽  
Vol 799-800 ◽  
pp. 734-738
Author(s):  
Tian Qi Dai ◽  
Shi Wei Yao ◽  
Zhi Guo Wei
Keyword(s):  
Thermal Effect ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Water Discharge ◽  
Cooling Water ◽  
Cross Flow ◽  
Pollution Prevention ◽  
Thermal Pollution ◽  
Thermal Discharge

The waste heat emissions of thermal discharge from floating nuclear power plants may have a negative thermal effect on the environment. Study on the dilution and diffusion of cooling water plays an important role in thermal pollution prevention. The cooling water discharge process can be condensed into the thermal jet in cross flow. According to the theory of computational fluid dynamics, the mathematical model of round horizontal thermal jets in cross flow is established. The 3D numerical simulation of thermal jets based on finite volume method is achieved by using the Realizable k-ε turbulence model and the Semi-implicit method for pressure linked equations, and the three-dimensional trajectory of thermal jet are obtained. The rationality of analysis method is approved by comparing calculation value with experimental value. The temperature distributions in thermal jets are studied through the numerical experiments conducted under different cross-flow velocity and different emission angle. As a result, the impacts of these conditions on thermal pollution area are found, and the theoretic bases are provided for the design of the cooling water discharge pipe.

scholarly journals HORIZONTAL DIFFUSION IN TIDAL MODELS AND SCALING CRITEREA FOR THERMAL-HYDRAULIC MODEL TESTS

1976 ◽  
Vol 1 (15) ◽  
pp. 176
Author(s):  
Gerd Flugge
Keyword(s):  
Nuclear Power ◽  
Waste Heat ◽  
Water Discharge ◽  
Electric Energy ◽  
Cooling Water ◽  
Model Tests ◽  
West Germany ◽  
Energy Output ◽  
Heat Output ◽  
Storm Tide

Near Brokdorf at the lower Elbe river (West Germany) a nuclear power plant is projected. The electric energy output shall be 1300 MWe; therefore the waste heat output will be about 2600 MWe. The maximum allowed temperature rise in the condenser amounts to 10 K. Accordingly the cooling water discharge is about 61 m /s in case of the provided once through cooling. For the purpose of the mixing and spreading of the discharged cooling water by mean tidal conditions and storm-tide conditions model tests have been carried out at the Franzius-Institut of the Technical University of Hannover.

scholarly journals FIELD STUDIES OF SUBMERGED-DIFFUSER THERMAL PLUMES WITH COMPARISONS TO PREDICTIVE MODEL RESULTS

1976 ◽  
Vol 1 (15) ◽  
pp. 172
Author(s):  
A.A. Frigo ◽  
R.A. Paddock ◽  
J.D. Ditmars
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Lake Michigan ◽  
Near Field ◽  
Cooling Water ◽  
Dimensional Structure ◽  
Field Region ◽  
Ambient Conditions ◽  
Thermal Plumes ◽  
Model Predictions

Thermal plumes from submerged discharges of cooling water from two power plants on Lake Michigan were studied. The system for the acquisition of water temperatures and ambient conditions permitted the three dimensional structure of the plumes to be determined. The Zion Nuclear Power Station has two submerged discharges structures separated by only 94 m. Under conditions of flow from both structures, interaction between the two plumes resulted in larger thermal fields than would be predicted by the superposition of single non-interacting plumes. Maximum temperatures in the near-field region of the plume compared favorably with mathematical model predictions. A comparison of physical-model predictions for the plume at the D. C. Cook Nuclear Plant with prototype measurements indicated good agreement in the near-field region, but differences in the far-field occurred as similitude was not preserved there.

scholarly journals SIMILARITY CONDITIONS FOR THERMAL-HYDRAULIC MODEL TESTS OF TIDAL ESTUARIES

1974 ◽  
Vol 1 (14) ◽  
pp. 142
Author(s):  
Gerd Flugge ◽  
Horst Schwarze
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Water Discharge ◽  
Free Surface Flow ◽  
Hydraulic Model ◽  
Surface Flow ◽  
Hot Water ◽  
Hydraulic Models ◽  
Tidal Estuaries ◽  
Dynamic Similitude

In connection with the design of proposed nuclear power plants on the Lower Weser River and on the Lower Elbe River in Germany, tidal models were constructed and tests carried out at the Franzius-Institute of the Technical University of Hannover for the purpose of studying the mixing and spreading of the hot water discharge. Thermal-hydraulic models are today still the most reliable method for the prediction of temperature distributions in the total area of temperature increase, especially in tidal regions. Hydraulic models with free surface flow are in general based on the FROUDE scaling lav;. The flow fields in both the hydraulic model and in the prototype show a dynamic similitude when the FROUDE numbers of the flow in the model and in the nature are equal at corresponding points.

The reactor research and test facility

2020 ◽  
pp. 69-79
Author(s):  
Andrey S. KIRILLOV ◽  
Aleksandr P. PYSHKO ◽  
Andrey A. ROMANENKO ◽  
Valery I. YARYGIN
Keyword(s):  
Measurement System ◽  
Nuclear Power ◽  
Power Plants ◽  
Test Facility ◽  
Physical Parameters ◽  
Pumping System ◽  
Current State ◽  
History Of ◽  
Special Measurement ◽  
Space Nuclear Power

The paper describes an overview of the history of development and the current state of JSC “SSC RF-IPPE” reactor research and test facility designed for assembly, research and full-scale life energy tests of space nuclear power plants with a thermionic reactor. The leading specialists involved in development and operation of this facility are represented. The most significant technological interfaces and upgrade operations carried out in the recent years are discussed. The authors consider the use of an oil-free pumping system as part of this facility during degassing and life testing. Proposed are up-to-date engineering solutions for development of the automated special measurement system designed to record NPP performance, including volt-ampere characteristics together with thermophysical and nuclear physical parameters of a ground prototype of the space nuclear power plant. Key words: reactor research and test facility, thermionic reactor, life energy tests, oil-free pumping system, automated special measurement system, volt-ampere characteristics.

HYDRAULIC MODEL EXPERIMENTS TO UNDERSTAND INFLUENCE OF UPCOAST STRUCTURES ON MEASURES AGAINST CLOGGING OF THE MOTOFUJI CALVERT

2019 ◽  
Vol 75 (2) ◽  
pp. I_541-I_546
Author(s):  
Masaki IKEDA ◽  
Hiroshige MATSUMOTO ◽  
Fumiaki ITO ◽  
Satoshi HENMI ◽  
Go ASANO
Keyword(s):  
Hydraulic Model ◽  
Model Experiments
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