Browse > Article
http://dx.doi.org/10.5855/ENERGY.2015.24.3.096

Preliminary Analysis of the Thermal-Hydraulic Performance of a Passive Containment Cooling System using the MARS-KS1.3 Code  

Bae, Sung Hwan (School of Mechanical Engineering, Pusan National University)
Ha, Tae Wook (School of Mechanical Engineering, Pusan National University)
Jeong, Jae Jun (School of Mechanical Engineering, Pusan National University)
Yun, Byong Jo (School of Mechanical Engineering, Pusan National University)
Jerng, Dong Wook (School of Energy System, Chung-Ang University)
Kim, Han Gon (Central Research Institute, Korea Hydro and Nuclear Power Co.)
Publication Information
Abstract
A passive containment cooling system has been designed to remove the heat inside a containment during accidents without external power supply. In this work, the PCCS was introduced in the APR1400 plant to replace the containment spray system and, then, the thermal-hydraulic performance of the PCCS was analyzed using the system thermal-hydraulic computer code, MARS. A double-ended cold-leg break accident, which is known to induce the maximum pressure in the containment, is simulated, where the thermal hydraulics of the PCCS, the reactor coolant system, and the containment are simultaneously simulated. The results of the calculations showed that the PCCS can replace the existing spray system and that the containment building and its internal structure also play a very important role for the heat removal during the accident. Some sensitivity calculations were carried out to evaluate the model uncertainty and the effects of design parameters. The limitations of the PCCS are also discussed.
Keywords
PCCS; MARS code; LOCA;
Citations & Related Records
연도 인용수 순위
  • Reference
1 한국과학기술원 원자력 및 양자공학과, "일본 후쿠 시마 원전 사고: 경과와 영향 그리고 교훈", 2001.
2 S.W. Lee, W.P. Baek, S.H Chang, "Assessment of Passive Containment Cooling Concepts for Advanced Pressurized Water Reactors", Ann. Nucl. Energy, 1997, Vol. 2, No. 6, pp. 467-475.   DOI
3 C.S. Byun, D.W. Jerng, N.E. Todreas, "Conceptual Design and Analysis of a Semi-passive Containment Cooling System for a Large Concrete Containment", Nuclear Engineering and Design, 2000, Vol. 199, pp. 227-242.   DOI
4 P.E. Juhn, J. Kupitz, J. Cleveland, "IAEA Activities on Passive Safety Systems and Overview of International Development", Nuclear Engineering and Design, 2000, Vol. 201, pp. 41-59.   DOI   ScienceOn
5 M.H. Anderson. L.E. Herranz, M.L. Corradini, "Experimental Analysis of Heat Transfer within the AP600 Containment under Postulated Accident Conditions", Nuclear Engineering and Design, 1998, Vol. 185, pp. 153-172.   DOI
6 T.L. Schulz, "Westinghouse AP1000 Advanced Passive Plant", Nuclear Engineering and Design, 2006, Vol. 236, pp. 1547-1557.   DOI
7 W.E. Cummins, M.M. Corletti, T.L. Schulz, "Westinghouse AP1000 Advanced Passive Plant", Proceedings of ICAPP, 2003, No. 3235.
8 V.V. Bezlepkin, M.A. Zatevakhin, O.P. Krektunoc, "Computational and Experimental Validation of a Passive Heat Removal System for NPP Containment with VVER-1200", Atomic energy, 2014, Vol. 115, No. 4.
9 N. Fil, "Status and Perspectives of VVER Nuclear Power Plants", Meeting of the TWG-LWR, 2011.
10 M. Kawakubo, M. Aritomi, H. Kikura, "An Experimental Study on the Cooling Characteristics of Passive Containment Cooling Systems", Journal of Nuclear Science and Technology, 2009, Vol. 46, pp. 339-345.   DOI
11 J.W. Kim, Y. G. LEE, H. K. Ahn, "Condensation Heat Transfer Characteristic in the Presence of Noncondensable Gas on Natural Convection at High Pressure", Nuclear Engineering and Design, 2009, Vol. 239, pp. 339-345.
12 H. Liu, N.E. Todreas, M.J. Driscoll, "An experimental investigation of a passive cooling unit for nuclear plant Containment", Nuclear Engineering and Design, 2000, Vol. 199, pp. 243-255.   DOI
13 Y.J. Cho, D.J. Euh, T.S. Kwon, "Preliminary Study on Design of Passive Containment Cooling System (PCCS)", Transactions of Korean Nuclear Society Spring Meeting, 2013.
14 G.H. Nam, J.S. Park, S.N. Kim, "Conceptual Design of a Thermosyphon with application to Passive Containment Cooling System for APR1400", The Korean Society of Mechanical Engineers, 2013, Vol. 12, pp. 3434-3439
15 하희운, VVER형 신개념 원전 PCCS 설계보고서, 한국수력원자력, 2012.
16 ANS Standard, "Decay Energy Release Rates Following Shutdown of Uranium-Fueled Thermal Reactors", 1973.
17 KHNP, APR1400 Standard Safety Analysis Report, 2005.
18 Korea Atomic Energy Research Institute, "MARS Code Manual Volume II: Input Requirements", 2009.