Pseudocritical Rapid Energy Dissipation Analysis of Base-Load Electrical Demand Reduction on Nuclear Steam Supply System
- 1 Graduate School of Nuclear and Allied Science, University of Ghana, Accra, Ghana
- 2 Nuclear Power Institute, Ghana Atomic Energy Commission, Accra, Ghana
- 3 Nuclear Power Institute, Ghana Atomic Energy Commission, Accra, Ghana
Abstract
Effect of pseudocritical rapid energy dissipation (PRED) from Pressurizer in nuclear steam supply system of Pressurized Water Reactor, where a single event as common cause failure, of considerable reduction of base-load electricity demand causes the temperature of the reactor coolant system (RCS) to increase, and corresponding pressure increases in pressurizer and steam generators above set-points. The study employed the uses of MATLAB/Simulink library tools, to experimentally modelled pressure control as PRED, where the momentum of transport of kinematic viscosity fraction above pseudocritical point dissipated as excess energy, to maintain the safety of the Pressurizer and RCS and keep the water from boiling. The result demonstrated the significance of pressure vector and Prandlt number as heat transfer coefficients that provided detailed activities in 2-D contour and 3-D graphics of specific internal energy and other parameterization of fluid in the pressurizer.
- Testa, D. and Kunkle, A. (1984) The Westinghouse Pressurized Water Reactor Nuclear Power Plant. Westinghouse Electric Corporation Water Reactor Divisions, 41-47.
- Ma, J., Chan, A. and Lv, L. (2012) Mathematical Modeling and Simulation of Pressurizer Pressure Control System. The 2 nd International Conference on Computer Application and System Modeling, Paris, 2012, 362-366. https://doi.org/10.2991/iccasm.2012.91
- IAEA (2004) Managing Modernization of Nuclear Power Plant Instrumentation and Control Systems IAEA. Vienna, 2004.
- IAEA (2011) Core Knowledge on Instrumentation and Control Systems in Nuclear Power Plants. IAEA Nuclear Energy Series Publications, Vienna.
- IAEA (2018) Approaches for Overall Instrumentation and Control Architectures of Nuclear Power Plants. IAEA Nuclear Energy Series No. NP-T-2.11 Vienna, Austria.
- Zhang, G.-D., Yang, X.-H., Ye, X.-L., Xu, H., Lu, D.-Q. and Chen, W. (2012) Research on Pressurizer Water Level Control of Pressurized Water Reactor Nuclear Power Station. Energy Procedia, 16, 849-855. https://doi.org/10.1016/j.egypro.2012.01.136
- Yang, S., Yi, P. and Habchi, C. (2020) Real-Fluid Injection Modeling and LES Simulation of the ECN Spray A Injector Using a Fully Compressible Two-Phase Flow Approach. International Journal of Multiphase Flow, 122, 103145. https://doi.org/10.1016/j.ijmultiphaseflow.2019.103145
- Troshko, A.A. and Hassan, Y.A. (2001) A Two-Equation Turbulence Model of Turbulent Bubbly Flow. International Journal of Multiphase Flow, 27, 1965-2000. https://doi.org/10.1016/S0301-9322(01)00043-X
- De Lorenzo, M., Lafon, P., Pelanti, M., Pantano, A., Di Matteo, M., Bartosiewicz, Y. and Seynhaeve, J.-M. (2021) A Hyperbolic Phase-Transition Model Coupled to Tabulated EoS for Two-Phase Flows in Fast Depressurizations. Nuclear Engineering and Design, 371, 110954. https://doi.org/10.1016/j.nucengdes.2020.110954
- Roth, G.A. and Aydogan, F. (2015) Derivation of New Mass, Momentum, and Energy Conservation Equations for Two-Phase Flows. Progress in Nuclear Energy, 80, 90-101. https://doi.org/10.1016/j.pnucene.2014.12.007
- Yadigaroglu, G. and Lahey Jr, R. (1976) On the Various Forms of the Conservation Equations in Two-Phase Flow. International Journal of Multiphase Flow, 2, 477-494. https://doi.org/10.1016/0301-9322(76)90011-2
- Krepper, E., Končar, B. and Egorov, Y. (2007) CFD Modelling of Subcooled Boiling—Concept, Validation and Application to Fuel Assembly Design. Nuclear Engineering and Design, 237, 716-731. https://doi.org/10.1016/j.nucengdes.2006.10.023