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http://dx.doi.org/10.5855/ENERGY.2018.27.4.027

Numerical Study of the Heat Removal Performance for a Passive Containment Cooling System using MARS-KS with a New Empirical Correlation of Steam Condensation  

Jang, Yeong-Jun (Department of Nuclear and Energy Engineering, Jeju National University)
Lee, Yeon-Gun (Department of Nuclear and Energy Engineering, Jeju National University)
Kim, Sin (School of Energy System Engineering, Chung-Ang University)
Lim, Sang-Gyu (Central Research Institute, Korea Hydro and Nuclear Power Co.)
Publication Information
Journal of Energy Engineering / v.27, no.4, 2018 , pp. 27-35 More about this Journal
Abstract
The passive containment cooling system (PCCS) has been designed to remove the released decay heat during the accident by means of the condensation heat transfer phenomenon to guarantee the safety of the nuclear power plant. The heat removal performance of the PCCS is mainly governed by the condensation heat transfer of the steam-air mixture. In this study, the heat removal performance of the PCCS was evaluated by using the MARS-KS code with a new empirical correlation for steam condensation in the presence of a noncondensable gas. A new empirical correlation implemented into the MARS-KS code was developed as a function of parameters that affect the condensation heat transfer coefficient, such as the pressure, the wall subcooling, the noncondensable gas mass fraction and the aspect ratio of the condenser tube. The empirical correlation was applied to the MARS-KS code to replace the default Colburn-Hougen model. The various thermal-hydraulic parameters during the operation of the PCCS follonwing a large-break loss-of-coolant-accident were analyzed. The transient pressure behavior inside the containment from the MARS-KS with the empirical correlation was compared with calculated with the Colburn-Hougen model.
Keywords
PCCS; MARS-KS code; condensation heat transfer; empirical correlation;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
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1 Li Y., et al., 2018, Numerical investigation of natural convection inside the containment with recovering passive containment cooling system using GASFLOW-MPI, Annals of Nuclear Energy, Vol. 114, pp. 1-10.   DOI
2 Li Y., et al., 2019, Numerical study of thermal hydraulics behavior on the integral test facility for passive containment cooling system using GASFLOWMPI, Annals of Nuclear Energy, Vol. 123, pp. 86-96.   DOI
3 Ha H. U., Lee S. W., Kim H. G., 2017, Optimal design of passive containment cooling system for innovative PWR, Nuclear Engineering and Technology, Vol. 49, pp. 941-952.   DOI
4 Bae S. H., et al., 2015, Preliminary analysis of the thermal-hydraulic performance of a passive containment cooling system using the MARS-KS1.3 code, KOSEE, Vol. 24, No. 3, pp. 96-108.
5 Lim S. G., et al., 2017, Prediction of heat removal performance for passive containment cooling system using MARS-KS code version 1.14, Korea Nuclear Society Spring Meeting, Jeju, May 18-19.
6 Colburn A. P., 1934, Design of cooler condenser for mixtures of vapors with noncondensable gases, Industrial & Engineering Chemistry, Vol. 26, pp. 1178-1182.   DOI
7 Jang Y. J., 2018, Experimental and numerical investigation of condensation heat transfer on the vertical tube under natural convection condition, Jeju National University, Ph. D. Dissertation, pp. 102-114.
8 Lee Y. G., Jang Y. J., Choi D. J., 2017, An experimental study of air-steam condensation on the exterior surface of a vertical tube under natural convection conditions, International Journal of Heat and Mass Transfer, Vol. 104, pp. 1034-1047.   DOI
9 Yoon D. S., Jo H. J., Corradini M. L., 2017, Assessment of MELCOR condensation models with the presence of noncondensable gas in natural convection flow regime, Nuclear Engineering and Design, Vol. 317, p. 110-117.   DOI
10 ANS Standard, 1973, Decay energy release rates following shutdown of uranium-fueled thermal reactors.
11 Jerong D. W., et al., 2015, A Study on Heat Transfer Model and Performance of Passive Systems for Nuclear Power Plant Containment Cooling.
12 Lee S. W., et al., 2017, The concept of the innovative power reactor, Nuclear Engineering and Technology, Vol. 49, pp. 1431-1441.   DOI
13 Choi D. J., 2015, Experimental and numerical investigation of condensation heat transfer coefficient on a vertical tube of Passive Containment Cooling System, Jeju National University, Master thesis, pp.30-39.
14 Bang H. M., 2017, Assessment of steam condensation model in MARS-KS with measured HTCs on vertical tube, Jeju National University, Master thesis, pp. 27-34.
15 Bang Y. S., et al., 2009, Improvements of condensation heat transfer models in MARS code for laminar flow in presence of non-condensable gas, Nuclear Engeeing and Technology., Vol. 41, pp. 1015-1024.   DOI
16 Cho Y. J., Euh D. J., Kwon T. S., 2013, Preliminary study of design of passive containment cooling system(PCCS), Korea Nuclear Society Spring Meeting, Gwangju, May 30-31.
17 Jeon B. G., No H. C., 2014, Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs, NED, Vol. 278, pp. 190-198.
18 Lee K. W., Cheong A. J., Shin A. D., 2016, Assessment of condensation heat trasnfer models of MARS-KS and TRACE codes using PASCAL test, Proceedings of the International Conference Nuclear Energy for New Europe, Portoroz, Slovenia, September 5-8.
19 Jingya L., Xiaoying Z., 2017, Simulation for cooling effect of PCCS in hot leg SB-LOCA of 1000 MW PWR, Nuclear Engineering and Design, Vol. 320, pp. 222-234.   DOI
20 Fernandez-Cosials K., et al., 2017, Three-dimensional simulaton of a LBLOCA in an AP1000 containment building, Energy Procedia, Vol. 127, pp. 234-241.   DOI