Thermal-hydraulic Analysis of Helical Coil Steam Generator of The Multi-Application Small Light Water Reactor (MASLWR) Test Loop Using Drift Flux Model
Subject Areas : Mechanical Engineering
Mansour
Talebi
1
(Nuclear Science & Technology Research Institute, Iran)
Valiyolah
Ghazanfari
2
(Nuclear Science & Technology Research Institute, Iran)
Keywords: Helical Coil Steam Generator, Thermal&ndash, Hydraulic, Drift Flux Model, MASLWR Reactor,
Abstract :
The Multi-Application Small Light Water Reactor (MASLWR) test loophas been built as a proof of concept for SMRs that is scaled down in size and has electric heater rods instead of a nuclear core. In this paper with using Drift-Flux Model (DFM), the thermal-hydraulic analysis of helical steam generator in MASLWR under steady-state conditions is simulated. This simulation is performed using the finite volume method. To ensure the accuracy and stability of solutions, User Defined Function (UDF) is written in C programming language. Distributions of velocities, local void fractions, temperature and pressure in the steam generator are calculated in different heights. To validate this simulation,the calculated primary side and secondary bulk fluid temperature are compared with experimental data. The experimental data have been provided by series of measurements of parameters of heat-transfer agent at Oregon State University. The calculated data are in good agreement with measured data and consequently the accuracy of this simulation is satisfied. Accuracy of the prediction shows that it is possible to use the DFM for thermal-hydraulic analysis in advanced models in nuclear power plant and other industries.
[1] Cooper, M., Small Modular Reactors and the Future of Nuclear Power in the United States, Energy Research & Social Science, Vol. 3, 2014, pp. 161-177.
[2] Reyes, J., Lorenzini, J., NuScale Power: A Modular, Scalable Approach to Commercial Nuclear Power. Nuclear News, Nuclear News, Vol. 6, 2012, pp. 97-103.
[3] Status of Small Reactor Designs without Onsite Refueling, INTERNATIONAL ATOMIC ENERGY AGENCY, Vienna, 2007.
[4] NuScale Power, 2012. [Online]. Available: https://www.nrc.gov/docs/ML1221/ML12216A392.pdf.
[5] Ingersoll, D., NuScale Small Modular Reactor for Co-Generation of Electricity and Water, Desalination, Vol. 34, 2014, pp. 84-93.
[6] NuScale Power Modular and Scalable Reactor, 2011. [Online]. Available: https://www.iaea.org/NuclearPower/Downloadable/aris/2013/26.NuScale.pdf.
[7] Lorenzo, S., Cioncolini, A., Lombardi, C., and Ricotti, M., Two-Phase Pressure Drops in a Helically Coiled Steam Generator, International Journal of Heat and Mass Transfer, Vol. 51, 2008, pp. 4926–4939.
[8] Colorado, D., Papini, D., Hernández, J., Santini, L., and Ricotti, M., Development and Experimental Validation of a Computational Model for a Helically Coiled Steam Generator, International Journal of Thermal Sciences, Vol. 50, 2011, pp. 569-580.
[9] Hee-Kyung, K., Hyoung, S., Chung, Y., and Kim, H., Thermal-Hydraulic Analysis of SMART Steam Generator Tube Rupture Using TASS/SMR-S Code, Annals of Nuclear Energy, Vol. 55, 2013, pp. 331-340.
[10] Mascaria, F., Vellaa, G., Woodsb, B., Welterc, K., Pottorfc, J., and Youngc, E., Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE, Nuclear Engineering and Design, Vol. 241, 2011, pp. 1137–1144.
[11] Bradyn, J., Comparative Analysis of the Zukauskas Method and Data from the OSU MASLWR Test Facility Steam Generator, 2014.
[12] Ghazanfari, V., Ansarifar, G., and Esteki, M., Drift Flux Modeling of the VVER-1000 Horizontal Nuclear Steam Generator, Progress in Nuclear Energy, Vol. 76, 2014, pp. 36-43.
[13] Ishii, M., Hibiki, T., Thermo-Fluid Dynamics of Two-Phase Flow, Springer, 2006.
[14] Hibiki, T., Ishii, M., One Dimensional Drift-Flux Model and Constitutive Equations for Related Motion Between Phases in Various Two-Phase Flow Regimes, International Journal of Heat Mass Transfer, Vol. 46, 2003, pp. 4935- 4948.