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KSME international journal v.18 no.5, 2004년, pp.820 - 829  

An Experimental Study on the Temperature Distribution in IRWST

Kim, Sang-Nyung   (Department of Nuclear Engineering, Kyunghee UniversityUU0001575  );
  • 초록

    The In-Containment Refueling Water Storage Tank (IRWST), one of the design improvements applied to the APR -1400, has a function to condense the high enthalpy fluid discharged from the Reactor Coolant System (RCS). The condensation of discharged fluid by the tank water drives the tank temperature high and causes oscillatory condensation. Also if the tank cooling water temperature approaches the saturated state, the steam bubble may escape from the water uncondensed. These oscillatory condensation and bubble escape would burden the undue load to the tank structure, pressurize the tank, and degrade its intended function. For these reasons simple analytical modeling and experimental works were performed in order to predict exact tank temperature distribution and to find the effective cooling method to keep the tank temperature below the bubble escape limit (93.3 $^{\circ}C$ ), which was experimentally proven by other researchers. Both the analytical model and experimental results show that the temperature distributions are horizontally stratified. Particularly, the hot liquid produced by the condensation around the sparger holes goes up straight like a thermal plume. Also, the momentum of the discharged fluid is not so strong to interrupt this horizontal thermal stratification significantly. Therefore the layout and shape of sparger is not so important as long as the location of the sparger hole is sufficiently close to the bottom of the tank. Finally, for the effective tank cooling it is recommended that the locations of the discharge and intake lines of the cooling system be cautiously selected considering the temperature distribution, the water level change, and the cooling effectiveness.


  • 주제어

    APR-1400 .   SDS .   IRWST Temperature Distribution .   Bubble Escape Temperature .   Thermal Stratification.  

  • 참고문헌 (15)

    1. Robert P. Benedict, 1977, Fundamentals of Temperature, Pressure and Flow Measurements, Wiley, pp. 443-469 
    2. Sangdeuk Park, 1996, 'Design Requirements and Features of Korean Next Generation Reactor, Center for Advanced Reactor Research of KEPRI,' Korea 
    3. KOPEC, 1996, 'IRWST T/H Load Analysis,' KEPCO, Korea     
    4. Kangyoul Bae, Hanshik Chung and Hyomin Jeong, 2002, 'Convective Heat Transfer in Ventilated Space with Various Partitions,' KSME Int. Jr., Vol. 16, No. 5, pp. 676-682     
    5. Koo-Woun Park, Se-Won Lee, Hee-Jin Ko and Young-Sik Jang, 1997, 'IRWST Hydrodynamic Loads in KNGR,' KOPEC, Korea 
    6. Korea Atomic Energy Research Institute, 1994, 'Joint Passive Safety Evaluation Program for System 80+,' 
    7. Korean Next Generation Reactor, Center for Advanced Reactor Research, 1994, 'Design Concept - The Total Plant Design (IV) 
    8. Kyungho Nam, Hejeon Ko and Jaeyoung Lim, 1996, 'IRWST System Design in KNGR,' Power Engineering, Vol. 7. No. 2, KOPEC 
    9. Lubin, B. T., 1991, 'Evaluation of the System 80+ Steam Relief System and IRWST Design.' 
    10. Cho, S.and Song, C. H., 2001, 'Multiple-Hole Effect on the Performance of a Sparger During Direct Contact Condensation of Steam,' KSME International Journal, Vol. 15, No. 4 
    11. Choong-Won Lee, Su-Yeon Moon, Chang-Hyun Sohn and Hyun-Jin Youn, 2003, 'Spray and Combustion Characteristics of a Dump-type Ramjet Combustor, Int. Jr., Vol. 17, No. 12, pp. 2019-2026     
    12. Combustion Engineering, 1994, 'System 80+ Standard Safety Analysis Report Design Certification,' Amendment W. 
    13. Heoyjung Kim, 1996, 'Safety Requirement in KNGR,' KINS 
    14. Holman, J. P., 1989, Experimental Method for Engineers, Fifth Edition, McGraw-Hill, pp 231-241 
    15. KEPCO, 1994, 'Elementary Requirement in KNGR.' 

 저자의 다른 논문

  • Kim, Sang-Nyung (9)

    1. 1990 "단상류와 이상류에서 펌프특성간의 상호관계 결정" 大韓機械學會論文集 14 (6): 1629~1638    
    2. 1991 "상반류(물/공기) 유동한계에 관한 연구" 大韓機械學會論文集 15 (1): 308~322    
    3. 1992 "배관내 자유수면에서 와류현상에 대한 연구" 大韓機械學會論文集 16 (11): 2126~2135    
    4. 1998 "피동형 원자로의 Hydraulic Valve 특성 실험" 大韓機械學會論文集. Transactions of the Korean Society of Mechanical Engineers. B. B 22 (8): 1083~1090    
    5. 2000 "Critical Velocity of Fluidelastic Vibration in a Nuclear Fuel Bundle" KSME international journal 14 (8): 816~822    
    6. 2001 "준등방성 적충복합재에 있어 압력이 압축 파괴인성에 미치는 영향에 대한 연구" 복합재료 : 한국복합재료학회지 = Journal of the Korean Society for Composite Materials 14 (3): 51~56    
    7. 2004 "The Analysis of Flow-Induced Vibration and Design Improvement in KSNP Steam Generators of UCN #5, 6" KSME international journal 18 (1): 74~81    
    8. 2004 "급수가열기 동체 감육 현상 규명을 위한 유동해석 연구" 한국액체미립화학회지 = Journal of ilass-korea 9 (4): 24~30    
    9. 2008 "EXPERIMENTAL AND ANALYTICAL STUDIES ON THE INSTABILITY IN THE LZCS FOR CANDU REACTORS" Nuclear engineering and technology : an international journal of the Korean Nuclear Society 40 (7): 561~570    

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