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Research Article

CFD validation of condensation heat transfer in scaled-down small modular reactor applications, Part 2: Steam and non-condensable gas

Palash Kumar BhowmikJoshua Paul Schlegel( )Varun KalraSyed AlamSungje HongShoaib Usman
Department of Nuclear Engineering and Radiation Science, Missouri University of Science and Technology, 1201 N. State St., Rolla, MO 65409, USA
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Abstract

This paper presents the computational fluid dynamics (CFD) validation and scaling assessment of the condensation heat transfer (CHT) models in the presence of non-condensable gas for the passive containment cooling system (PCCS) of the small modular reactor (SMR). The STAR-CCM+ software with 3D scaled-down SMR containment geometries was used in CFD simulations with steam and non-condensable gas (NCG). The limitations and approximations of the previous studies were resolved to avoid scaling distortion and uncertainties. Air was used as the NCG gas with steam. The multi-component gas model was used to define the steam–NCG mixture, and the condensation-seed parameter was used as the source term for the fluid film model. Three different turbulence models were used to check the heat flux performances and temperature distributions on the coolant side. The heat flux was estimated from the axial coolant bulk temperature, which was identical to the test data reduction method. An implicit-unsteady numerical solver was applied to the conjugate heat transfer models between the gas, liquid, and solid regions. Detailed simulations were performed, and simulation results were validated with the measured parameters experimentally. The condensation heat transfer performance was quantified using non-dimensional numbers and compared for different scaled geometries to identify the scaling distortions.

References

 
Ahammad, F., Mahmud, S., Islam, S. Z. 2019. Computational fluid dynamics study of yield power law drilling fluid flow through smooth-walled fractures. J Petrol Explor Prod Technol, 9: 2717–2727.
 
Ahmed, F., Ara, N., Deshpande, V., Mollah, A., Bhowmik, P. K. 2021a. CFD validation with optimized mesh using benchmarking data of pebble-bed high-temperature reactor. Prog Nucl Energy, 134: 103653.
 
Ahmed, F., Abir, M. A., Bhowmik, P. K., Deshpande, V., Mollah, A. S., Kumar, D., Alam, S. 2021b. Computational assessment of thermo- hydraulic performance of Al2O3-water nanofluid in hexagonal rod-bundles subchannel. Prog Nucl Energy, 135: 103700.
 
Alam, S. B., Kumar, D., Almutairi, B., Bhowmik, P. K., Goodwin, C., Parks, G. T. 2019. Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part I: Assembly-level analysis. Nucl Eng Des, 346: 157–175.
 
Bhowmik, P. K. 2016. Nanofluid operation and valve engineering of SUPER for small unit passive enclosed reactor. Master Thesis. Seoul National University, Republic of Korea.
 
Bhowmik, P. K., Schlegel, J. P., Kalra, V., Mills, C., Usman, S. 2021a. Design of condensation heat transfer experiment to evaluate scaling distortion in small modular reactor safety analysis. J Nuclear Rad Sci, 7: 031406.
 
Bhowmik, P. K., Schlegel, J., Kalra, V., Alam, S., Hong, S., Usman, S. 2021b. CFD validation of condensation heat transfer in scaled-down small modular reactor applications, Part 1: Pure steam. Exp Comput Mulitph Flow, .
 
Bhowmik, P. K., Shamim, J. A., Chen, X., Suh, K. Y. 2021c. Rod bundle thermal-hydraulics experiment with water and water-Al2O3 nanofluid for small modular reactor. Ann Nucl Energy, 150: 107870.
 
Bhowmik, P. K., Suh, K. Y. 2021. Flow mapping using 3D full-scale CFD simulation and hydrodynamic experiments of an ultra- supercritical turbine’s combined valve for nuclear power plant. Int J Energy Env Eng, .
 
Bian, H., Sun, Z., Ding, M., Zhang, N. 2017. Local phenomena analysis of steam condensation in the presence of air. Prog Nucl Energy, 101: 188–198.
 
Buongiorno, J., Corradini, M., Parsons, J., Petti, D. 2019. Nuclear energy in a carbon-constrained world: Big challenges and big opportunities. IEEE Power Energy Mag, 17: 69–77.
 
Cheng, X., Bazin, P., Cornet, P., Hittner, D., Jackson, J., Jimenez, J. L., Naviglio, A., Oriolo, F., Petzold, H. 2001. Experimental data base for containment thermalhydraulic analysis. Nucl Eng Des, 204: 267–284.
 
Dehbi, A., Janasz, F., Bell, B. 2013. Prediction of steam condensation in the presence of noncondensable gases using a CFD-based approach. Nucl Eng Des, 258: 199–210.
 
Fu, W., Li, X., Wu, X., Corradini, M. L. 2016. Numerical investigation of convective condensation with the presence of non-condensable gases in a vertical tube. Nucl Eng Des, 297: 197–207.
 
Gharari, R., Kazeminejad, H., Kojouri, N. M., Hedayat, A. 2018. A review on hydrogen generation, explosion, and mitigation during severe accidents in light water nuclear reactors. Int J Hydrog Energy, 43: 1939–1965.
 
Hasan, F., Al Mahmud, K. A. H., Khan, M. I., Patil, S., Dennis, B. H., Adnan, A. 2021. Cavitation induced damage in soft biomaterials. Multiscale Sci Eng, 3: 67–87.
 
Huang, J., Zhang, J., Wang, L. 2015. Review of vapor condensation heat and mass transfer in the presence of non-condensable gas. Appl Eng, 89: 469–484.
 
IAEA. 2018. Advances in small modular reactor technology developments. Austria: IAEA.
 
Khan, M. I., Billah, M. M., Rahman, M. M., Hasan, M. N. 2017. Mixed convection heat transfer simulation in a rectangular channel with a variable speed rotational cylinder, In: Proceedings of the AIP Conference.
 
Kuhn, S. Z. 1995. Investigation of heat transfer from condensing steam-gas mixtures and turbulent films flowing downward inside a vertical tube. Ph.D. Thesis. University of California, USA.
 
Li, J. D. 2013. CFD simulation of water vapour condensation in the presence of non-condensable gas in vertical cylindrical condensers. Int J Heat Mass Transf, 57: 708–721.
 
Mahaffy, J., Chung, B., Song, C., Dubois, F., Graffard, E., Ducros, F., Heitsch, M., Scheuerer, M., Henriksson, M., Komen, E., Moretti, F., Morii, T., Muehlbauer, P., Rohde, U., Smith, B. L., Watanabe, T., Zigh, G. 2007. Best practice guidelines for the use of CFD in nuclear reactor safety applications. Nuclear Energy Agency of the OECD (NEA).
 
Malet, J., Porcheron, E., Vendel, J. 2010. OECD international standard problem ISP-47 on containment thermal-hydraulics—Conclusions of the TOSQAN part. Nucl Eng Des, 240: 3209–3220.
 
Milinchuk, V., Klinshpont, E. R., Belozerov, V., Zagorodnyaya, A. 2017. Hydrozirconium reaction in heterogeneous compositions. Nucl Energy Technol, 3: 15–18.
 
Mishra, A. A., Girimaji, S. S. 2013. Intercomponent energy transfer in incompressible homogeneous turbulence: Multi-point physics and amenability to one-point closures. J Fluid Mech, 731: 639–681.
 
Nian, V., Chou, S. 2014. The state of nuclear power two years after Fukushima—The ASEAN perspective. Appl Energy, 136: 838–848.
 
Power Reactor Information System (PRIS). 2019. The database on nuclear power reactors. International Atomic Energy Agency, Austria. Available at https://pris.iaea.org/pris/.
 
Ravva, S. R., Iyer, K. N., Gupta, S., Gaikwad, A. J. 2014. Implementation and validation of the condensation model for containment hydrogen distribution studies. Nucl Eng Des, 270: 34–47.
 
Ritchie, H. 2018. What are the safest and cleanest sources of energy? Available at https://ourworldindata.org/safest-sources-of-energy.
 
Saha, S., Khan, J., Farouk, T. 2020. Numerical study of evaporation assisted hybrid cooling for thermal powerplant application. Appl Therm Eng, 166: 114677.
 
Shamim, J. A., Bhowmik, P. K., Chen Y. X., Suh, K. Y. 2016. A new correlation for convective heat transfer coefficient of water–alumina nanofluid in a square array subchannel under PWR condition. Nucl Eng Des, 308: 194–204.
 
Sharma, P. K., Gera, B., Singh, R. K., Vaze, K. K. 2012. Computational fluid dynamics modeling of steam condensation on nuclear containment wall surfaces based on semiempirical generalized correlations. Sci Technol Nucl Install, 2012: 1–7.
 
Sharma, S. L., Ishii, M., Hibiki, T., Schlegel, J. P., Liu, Y., Buchanan, J. R. 2019. Beyond bubbly two-phase flow investigation using a CFD three-field two-fluid model, Int J Multiph Flow, 113: 1–15.
 
Su, J., Sun, Z., Zhang, D. 2014. Numerical analysis of steam condensation over a vertical surface in presence of air. Ann Nucl Energy, 72: 268–276.
 
Tagami, T. 1965. Interim Report on Safety Assessments and Facilities Establishment Project in Japan for Period Ending June 1965 (No. 1).
 
Uchida, H., Oyama, A., Togo, Y. 1964. Evaluation of post-incident cooling systems of light-water power reactors. In: Proceedings of the 3rd International Conference on the Peaceful Uses of Atomic Energy, USA.
 
Wheatley, S., Sovacool, B. K., Sornette, D. 2016. Reassessing the safety of nuclear power. Energy Res Soc Sci, 15: 96–100.
 
Yeoh, G. H. 2019. Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges. Exp Comput Multiph Flow, 1: 3–27.
 
Zschaeck, G., Frank, T., Burns, A. 2014. CFD modelling and validation of wall condensation in the presence of non-condensable gases. Nucl Eng Des, 279: 137–146.
Experimental and Computational Multiphase Flow
Pages 424-434
Cite this article:
Bhowmik PK, Schlegel JP, Kalra V, et al. CFD validation of condensation heat transfer in scaled-down small modular reactor applications, Part 2: Steam and non-condensable gas. Experimental and Computational Multiphase Flow, 2022, 4(4): 424-434. https://doi.org/10.1007/s42757-021-0113-7

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Received: 20 January 2021
Revised: 30 March 2021
Accepted: 14 May 2021
Published: 21 July 2021
© Tsinghua University Press 2021
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