Journal of Energy Engineering (에너지공학)

The Korean Society for Energy (한국에너지학회)
권호 표지
DOI QR코드

DOI QR Code

Development of a thermal-hydraulic analysis code for once-through steam generators using straight tubes for SMRs

일체형 원자로용 관류식 직관형 증기발생기 열수력 해석 코드 개발

  • Park, Youngjae (Department of Nuclear Engineering, Kyung Hee University) ;
  • Kim, Iljin (Department of Nuclear Engineering, Kyung Hee University) ;
  • Kang, Kyungjun (Department of SMART development, Korea Atomic Energy Research Institute) ;
  • Kang, Hanok (Department of SMART development, Korea Atomic Energy Research Institute) ;
  • Kim, Youngin (Department of SMART development, Korea Atomic Energy Research Institute) ;
  • Kim, Hyungdae (Department of Nuclear Engineering, Kyung Hee University)
  • 박영재 (경희대학교 원자력공학과) ;
  • 김일진 (경희대학교 원자력공학과) ;
  • 강경준 (한국원자력연구원 SMART 개발부) ;
  • 강한옥 (한국원자력연구원 SMART 개발부) ;
  • 김영인 (한국원자력연구원 SMART 개발부) ;
  • 김형대 (경희대학교 원자력공학과)
  • Received : 2015.01.16
  • Accepted : 2015.04.17
  • Published : 2015.06.30
Download PDF
⟨ Previous Next ⟩

Abstract

A thermal-hydraulic design and performance analysis computer code for a once-through steam generator using straight tubes is developed. To benchmark the developed physical models and computer code, an once-through steam generator developed by other designer is simulated and the calculated results are compared with the design data. Also, the same steam generator is analyzed with the best-estimate thermal-hydraulic system code, MARS, for the code-to-code validation. The overall characteristics of heat transfer area, pressure and temperature distributions calculated by the developed code show general agreements with the published design data as well as the analysis results of MARS. It is demonstrated that the developed code can be utilized for diverse purposes, such as, sensitivity analyses and optimum thermal design of a once-through steam generator.

관류식 직관형 증기발생기의 열수력 설계와 성능분석을 위한 해석코드를 개발하였다. 개발한 물리적 모델과 수치 해석 코드를 검증하기 위해 설계 제원이 공개되어 사용되고 있는 관류식 직관형 증기발생기를 개발된 코드를 이용해 해석하고 설계 자료와 비교하였다. 또한 동일한 증기발생기를 최적 열수력 안전해석코드인 MARS를 이용하여 해석한 뒤 비교분석하였다. 열전달면적, 압력 및 온도분포 등의 계산 결과는 설계 자료 및 MARS 코드의 계산 결과와 대부분 일치하게 나타났다. 최종적으로 개발된 코드가 직관형 증기발생기의 열적 설계 최적화 및 민감도 분석을 목적으로 폭넓게 사용될 수 있음을 확인하였다.

Keywords

References

  1. IAEA: "Status report 77 - System-integrated modular reactor (SMART)", (2011)
  2. Carelli, M.D., Conway, L.E., Oriani, L., Petrovic, B., Lombardi, C.V., Ricotti, M.E., Barroso, A.C.O., Collado, J.M., Cinotti, L., Todreas, N.E., Grgic, D., Moraes, M.M., Boroughs, R.D., Ninokata, H., Ingersoll, D.T., Oriolo, F.: "The design and safety features of the IRIS reactor", Nuclear Engineering and Design, vol. 230, 151-167, (2004) https://doi.org/10.1016/j.nucengdes.2003.11.022
  3. IAEA: "Status of small and medium sized reactor designs - a supplement to the IAEA advanced reactors information system", (2012)
  4. IAEA: "Status report 106 - NuScale power modular and scalable reactor (NuSclae)", (2011)
  5. Magan, H. B., Delmastro, D.F., Markiewicz, M., Lopasso, E., Diez, F., Gimenez, M., Rauschert, A., Halpert, S., Chocrón, M., Dezzutti, J.C., Pirani, H., Balbi, C., Fittipaldi, A., Schlamp, M., Murmis, G.M., and Lis, H.: "CAREM project status", Science and Technology of Nuclear Installations, 140373, 6, (2011)
  6. White paper of nuclear energy, Ministry of Science, ICT, and Future Planning, in Korean, (2014)
  7. KAERI, KEPCO consortium, "The new flagship product of Korean nuclear energy, SMART reactor", Press kit for standard design approval of SMART reactor, in Korean, (2013)
  8. The RELAP5 Development Team: "RELAP5/MOD3 Code Manual: models and correlations", NUREG/CR-5535, INEL-95/0174, (1995)
  9. KAERI: "MARS code manual: models and correlations", KAERI/TR-3872/2009, (2010)
  10. Yoon, J., Kim, J.P., Kim, H.Y., Lee, D.J., Chang, M.H.: "Development of a computer code, ONCESG, for the thermal-hydraulic design of a once-through steam generator", Journal of NUCLEAR SCIENCE and TECHNOLOGY, vol. 37, no. 5, 445-454, (2000) https://doi.org/10.1080/18811248.2000.9714917
  11. Green, S.J., and Hetsroni, G.: "PWR steam generators", Int. J. Multiphase Flow, vol. 21, 1-97, (1995)
  12. McAdams, W.H., Woods, W.K., Heroman, L.C.: "Vaporization inside horizontal tubes II : benzene- oil mixtures", Trans. ASME, vol. 64, no. 3, 193-200, (1942)
  13. Incropera, F.P., DeWitt, D.P., Bergman, T.L., Lavine, A.S.: "Introduction to Heat Transfer", 5th Edition, John Wiley & Sons, Inc., (2007)
  14. Petukhov, B.S.: "Heat transfer and friction in turbulent pipe flow with variable physical properties", in Advances in Heat Transfer, J. P. Hartnett and T. F. Irvine, Eds., pp. 504-564, Academic Press, New York, NY, USA, (1970)
  15. Chen, J.C.: "Correlation for boiling heat transfer to saturated fluids in convective flow", I&EC PROCESS DESIGN AND DEVELOPMENT, vol. 5, no. 3, 322, (1996)
  16. Kitto. J.B. and Stultz., S.C.: "Steam: its generation and use", The Babcock & Wilcox Company, (2005)
  17. Chaxton, K.T., Collier, J.G. and Ward, J.A.: "H.T.F.S. correlation for two-phase pressure drop and void fraction in tubes", AERE-R7162. (1972)
  18. Lockhart, R.W. and Martinelli, R.C.: "Proposed correlation of data for isohtermal two-phase, two-component flow in pipes", Chemical Engineering Progress, vol. 45, no. 1, 39-48, (1949)
  19. Fetterman, R.J., Harkness, A.W., Smith, M.C. and Taylor, C.: "An overview of the westinghouse small modular reactor", ASME 2011 Small Modular Reactors Symposium, Washington, DC, USA, September 28-30, (2011)