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Method and Program to Calculate the Speed of Sound in Water under the Conditions of Natural Convection along the Surface of Fuel Assemblies of Nuclear Reactors

https://doi.org/10.1134/S2304487X19050080

Abstract

   The principle of the ultrasonic method for determining fuel assemblies forming in cooling pond of nuclear power plants is considered. It is shown that natural convection caused by residual heat generation affects the increase in the measurement error of the ultrasonic method. A method is proposed for calculating the convective heat transfer with the boundary condition of the second kind. The developed method has been tested by performing calculations under the conditions of experiments in which temperature change in water inside a free convective laminar and turbulent thermal boundary layer has been studied. Analysis of experimental and calculated data shows that the method used adequately describes natural-convection heat transfer. Using this method, an algorithm and a program are developed for calculating the speed of sound in water in a laminar and turbulent boundary layer near the surface of a vertical heated plate, simulating in the first approximation the heated surface of a WWER-1000 FA. The developed program also computes the parameters of the boundary layer, heating temperature, and temperature profile along the acoustic axis of the ultrasonic sensor. The program can be used to approximately estimate the influence of convection on measurement results and to verify CFD codes as applied to the calculation of the parameters of natural convection at the surface of the WWER-1000 FA, taking into account the decay heat.

About the Authors

A. V. Voronina
Dimitrovgrad Engineering and Technological Institute, National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)
Russian Federation

433510

Ulyanovsk oblast

Dimitrovgrad



S. V. Pavlov
Dimitrovgrad Engineering and Technological Institute, National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)
Russian Federation

433510

Ulyanovsk oblast

Dimitrovgrad



References

1. Ivanov N. A., Bromirskii I. A., Surov D. V., Pervushin L. A., Tishkov A. N., Sementsov A. V., Pavlov S. V., Amosov S. V., Stend inspekcii i remonta teplovy`delyayushhix sborok dlya proekta AE`S – 2006 [Fuel repair and inspection equipment for AES-2006 NPP design]. Tyazheloe mashinostroenie (ISSN: 1024-7106), 2017, no. 4, pp. 25–28 (in Russian).

2. Pavlov S. V., Sukhikh A. V., Sakharov S. S. Nerazrushayushchaya diagnostika sostoyaniya elementov aktivnykh zon yadernykh reaktorov [Non-destructive diagnostics of the state of core elements of nuclear reactors]. Dimitrovgrad: DITI MIFI, 2015. 320 p.

3. Voronina A. V. Analiz e`ffektivnosti, nadezhnosti i bezopasnosti metodov opredeleniya formoizmeneniya TVS VVE`R-1000 na AE`S [Analysis of the effectiveness, reliability and safety of methods for determining the forming WWER-1000 NPP]. Vserossijskaya molodyozhnaya konferenciya “Nauchny`e issledovaniya i texnologicheskie razrabotki v obespechenii razvitiya yaderny`x texnologij novogo pokoleniya” [All-Russian Youth Conference “Scientific research and technological development to ensure the development of nuclear technologies of new generation”]. Dimitrovgrad: JSC “SSC RIAR”, 2018, pp. 62–64 (in Russian).

4. Dvoreczkij V. G., Ivanov V. B., Glushak N. S. Metodiki izmereniya geometricheskij razmerov i formy` chexla TVS [Methods for measuring the geometric dimensions and shape of fuel assembly outer jacket]. Dimitrovgrad: RIAR, 1991. 19 p.

5. Pavlov S. V. Nerazrushayuschie ultrazvukovie metodi issledovanii obluchennogo topliva yadernih reaktorov [Non-destructive ultrasonic research methods of irradiated fuel of nuclear reactors]. Dimitrovgrad: JSC “SSC RIAR”, 2013. 256 p.

6. Pavlov S. V. Metody` i sredstva issledovanij TVS VVE`R dlya e`ksperimental`nogo soprovozhdeniya vnedreniya novogo topliva na AE`S [Methods and tools for research of VVER fuel assemblies for experimental support of the introduction of new fuel at nuclear power plants. Dr. eng. sci. diss.]. Dimitrovgrad, 2015. 339 p.

7. Brazhnikov N. I. Ul`trazvukovy`e metody` [Ultrasonic methods]. In Shumilovskogo N. N. (ed.), Moscow, Leningrad: Energiya, 1965. 248 p.

8. Pavlov S. V., Shalaginova T. M., Mikhailov S. V., Prokudanov D. L. Issledovanie vliyaniya estestvennoj konvekcii na rezul`taty` izmereniya geometricheskix xarakteristik tve`lov i teplovy`delyayushhix sborok ul`trazvukovy`mi metodami v usloviyax bassejnov vy`derzhki [Investigation of the effect of natural convection on the results of measuring the geometric characteristics of fuel rods and fuel assemblies by ultrasonic methods in conditions of cooling pond]. Dimitrovgrad: RIAR, 1991. 28 p.

9. Pavlov S. V., Voronina A. V. Programma dlya rascheta skorosti zvuka v vode u poverxnosti vertikal`noj nagretoj plastiny` [The program for calculating the speed of sound in water at the surface of a vertical heated plate]. The certificate of the Russian Federation no. 2018660777 about the state registration of the computer program, 2018.

10. Orlov K. A., Aleksandrov A. A., Ochkov A. V., Ochkov V. F. The certificate of the Russian Federation no. 2000610803 about official registration of the computer program WaterSteamPro, 2011.

11. Lykov A. V. Teplomassoobmen: Spravochnik [Heat and Mass Transfer: A Handbook]. 2-e izd.: Moscow: Energiya, 1978. 480 p.

12. Dzhaluriya I. Estestvennaya konvekciya. Teplo- i massoobmen [Natural convection. Heat and mass transfer]. Moscow: Mir, 1983. 399 p.

13. Vliet G. C., Liv C. K. An Experimental Study of Turbulent Natural Convection Boundary Layers, Journal of Heat Transfer, 1969, no. 4, pp. 73–96.

14. Gebhart В. Transition and transport in a buoyancy driven flow in water adjacent to a vertical uniform flux surface, Int. J. Heat Mass Transform, 1978, vol. 21, pp.1467–1479.


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For citations:


Voronina A.V., Pavlov S.V. Method and Program to Calculate the Speed of Sound in Water under the Conditions of Natural Convection along the Surface of Fuel Assemblies of Nuclear Reactors. Vestnik natsional'nogo issledovatel'skogo yadernogo universiteta "MIFI". 2019;8(5):465-472. (In Russ.) https://doi.org/10.1134/S2304487X19050080

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