Computational Fluid Dynamics Applied to Study Coolant Loss Regimes in Very High Temperature Reactors
DOI:
https://doi.org/10.15392/bjrs.v9i2A.683Keywords:
VHTR, Pebble Bed Reactor, CFDAbstract
The nuclear energy is a good alternative to meet the continuous increase in world energy demand. In this pers-pective, VHTRs (Very High Temperature Reactors) are serious candidates for energy generation due to its inherently safe performance, low power density and high conversion efficiency. However, the viability of these reactors depends on an efficient safety system in the operation of nuclear plants. The HTR (High Temperature Reactor)-10 model, an experimental reactor of the pebble bed type, is used as a case study in this work to perform the thermohydraulic simulation. Due to the complex patterns flow that appear in the pebble bed reactor core CFD (Computational Fluid Dynamics) techniques are used to simulate these reactors. A realistic approach is adopted to simulate the central annular column of the reactor core. As geometrical model of the fuel elements was selected the BCC (Body Centered Cubic) arrangement. Parameters considered for reactor design are available in the technical report of benchmark issues by IAEA (TECDOC-1694). We obtain the temperature profile distribution in the core for regimes where the coolant flow rate is smaller than recommended in a normal operation. In general, the temperature distributions calculated are consistent with phenomenological behavior. Even without considering the reactivity changes to reduce the reactor power or other safety mechanisms, the maximum temperatures do not exceed the recommended limits for TRISO fuel elements.
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References
GIF – Generation IV International Forum. A Technology Roadmap for Generation IV Nuclear Energy Systems, 2002. 112p.
IAEA – International Atomic Energy Nuclear. Evaluation of High Temperature Gas Cooled Reactor Performance: benchmark analysis related to the PBMR-400, PBMM, GT-MHR, HTR-10 and the ASTRA critical facility, Vienna, 2013. 675p.
GÁMEZ, A.; MAZAIRA, L. Y. R.; DOMINGUEZ, D. S.; ROSALES, J.; CASTRO, L. Y.; GONZÁLEZ, D.; GARCIA, C.; OLIVEIRA, C. B. Computational Fluid Dynamic Model for Thermohydraulic Calculation for the Steady-State of the Real Scale HTR-10, In: IN-TERNATIONAL NUCLEAR ATLANTIC CONFERENCE, São Paulo, 2015.
WU, C. Y.; FERNG, Y. M., CHIENG, C. C., LIU, C. C. Investigating the advantages and disadvantages of realistic approach and porous approach for closely packed pebbles in CFD simulation. Nuclear Engineering and Design, v. 240, p. 1151-1159, 2010.
SILVA, A. S.; MAZAIRA, L. Y. R., DOMINGUEZ, D. S.; HERNÁNDEZ, C. R. G.; LI-RA, C. A. B. O. Uso de Arranjos Cúbicos na Simulação Realística CFD do Núcleo do Rea-tor HTR-10, In: XIX ENMC - National Meeting on Computacional Modeling and VII ECTM - Meeting on Materials Science and Technology, João Pessoa, 2016.
SILVA, A. S. Modelagem Termohidráulica de Sistemas Nucleares de Temperatura Muito Elevada do tipo Leito de Bolas usando Dinâmica de Fluídos Computacional, Ilhéus, 2016. 87p.
FERNG, Y. M.; CHI, C. W. Investigating effects of BCC and FCC arrangements on flow and heat transfer characteristics in pebbles through CFD methodology. Nuclear Enginee-ring and Design, v. 258, p. 66-75, 2013.
FERNG, Y. M.; LIN, K. Y. CFD investigating the air ingress accident for a HTGR simula-tion of graphite corrosion oxidation. Nuclear Engineering and Design, v. 248, p. 55-65, 2012.
FERNG, Y. M.; CHI, C. W. CFD investigating the air ingress accident occurred in a HTGR simulation of thermal-hydraulic characteristics. Nuclear Engineering and Design, v. 245, p. 28-38, 2012.
HAM, T. K.; ARCILESI JR., D. J.; KIM, I. H.; SUN, X.; CHRISTENSEN, R. N.; OH, C. H.; KIM, E. S. Computational fluid dynamics analysis of the initial stages of a VHTR air-ingress accident using a scaled-down model. Nuclear Engineering and Design, v. 300, p. 517-529, 2016.
WU, H.; GUI, N.; YANG, X.; TU, J. Numerical simulation of heat transfer in packed pebble beds: CFD-DEM coupled with particle thermal radiation. International Journal of Heat and Mass Transfer, v. 110, p. 393-405, 2017.
U. S. NUCLEAR REGULATORY COMISSION. TRISO-Coated Particle Fuel Pheno-menon Identification and Ranking Tables (PIRTS) for Fission Product Transport Due to Manufacturing, Operations and Accidents, Washington, 2004. 588p.
VERSTEEG, K. H.; MALALASEKERA, W. An Introduction to Computational Fluid Dynamics: The Finite Volume Method, 2rd ed. Harlow: Pearson Education, 2007.
ANSYS INC. Ansys CFX R14 Pre-User's Guide, Canonsburg, 2011. 342p.
TU, J.; LIU, C. Computacional Fluid Dynamics: A Pratical Approach, 2rd ed., Oxford: Butterworth-Heinemann, 2013.
KTA – Nuclear Safety Standards Commission. Reactor Core Design for High-Temperature Gas-Cooled Reactor Part 1: Calculation of the Material Properties of He-lium, Salzgitter, 1978. 2p.
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