에너지공학 (Journal of Energy Engineering)

  • 제23권4호
  • /
  • Pages.95-105
  • /
  • 2014
  • /
  • 1598-7981(pISSN)
  • /
  • 2713-7074(eISSN)
한국에너지학회 (The Korean Society for Energy)
권호 표지
DOI QR코드

DOI QR Code

CUPID 코드를 이용한 CANDU 원자로 칼란드리아 탱크 내부유동 열수력 예비 해석

Preliminary Thermal-Hydraulic Analysis of the CANDU Reactor Moderator Tank using the CUPID Code

  • 투고 : 2014.10.10
  • 심사 : 2014.12.05
  • 발행 : 2014.12.31
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

CUPID 코드는 기기 스케일(Component scale)의 2상 유동(Two-phase flow) 해석 코드로서 다양한 2상 유동 조건의 실험 자료를 이용하여 검증되어 왔다. 특히, CUPID 코드의 CANDU형 원자로 감속재 탱크 내부 유동 해석능력을 평가하기 위해 1/4 규모 축소 실험장치의 실험결과를 이용하여 검증한 바가 있다. 본 연구에서는 이전 연구를 바탕으로 CUPID 코드를 사용하여 실제 원자로 감속재탱크 내부의 열수력 거동을 해석하였다. 감속재 탱크의 내부 구조는 아주 복잡하기 때문에 다공질 매질 방법을 적용하였으며 탱크 입구노즐 또한 기기 스케일 코드의 취지에 부합하게 아주 단순화하여 모델하였다. 해석결과의 정확성을 결정하는 가장 중요한 요소는 입구노즐의 모델 방법에 있는 것으로 나타났다. 입구노즐을 단순하게 모델하여 입구유량을 경계조건으로 부여하고 발전소 정상운전조건으로 계산한 결과, 부력에 의한 열성층화 현상이 발생하였다. 이는 전혀 타당하지 않은 것으로 입구 유동의 모멘텀을 정확하게 모의하지 않아 발생한 것이 나타났다. 이를 개선하고자 입구 유량과 운동량을 동시에 보존시킬 수 있도록 입구 노즐 면적을 축소하고 속도는 증가시켜서 계산한 결과, 사실적인 내부 유동장을 얻을 수 있었다. 결론적으로 계산 비용효과가 뛰어난 다공질 매질 방법에 입각하여 CUPID 코드를 실규모 감속재 탱크 열유동 해석에 적용할 수 있음을 보였고, 입구노즐의 적절한 모델이 가장 중요한 요소임을 확인하였다.

The CUPID code has been developed for a transient, three-dimensional, two-phase flow analysis at a component scale. It has been validated against a wide range of two-phase flow experiments. Especially, to assess its applicability to single- and two-phase flow analyses in the Calandria vessel of a CANDU nuclear reactor, it was validated using the experimental data of the 1/4-scaled facility of a Calandria vessel at the STERN laboratory. In this study, a preliminary thermal-hydraulic analysis of the CANDU reactor moderator tank using the CUPID code is carried out, which is based on the results of the previous studies. The complicated internal structure of the Calandria vessel and the inlet nozzle was modeled in a simplified manner by using a porous media approach. One of the most important factors in the analysis was found to be the modeling of the tank inlet nozzle. A calculation with a simple inlet nozzle modeling resulted in thermal stratification by buoyance, leading to a boiling from the top of the Calandria tank. This is not realistic at all and may occur due to the lack of inlet flow momentum. To improve this, a new nozzle modeling was used, which can preserve both mass flow and momentum flow at the inlet nozzle. This resulted in a realistic temperature distribution in the tank. In conclusion, it was shown that the CUPID code is applicable to thermal-hydraulic analysis of the CANDU reactor moderator tank using the cost-effective porous media approach and that the inlet nozzle modeling is very important for the flow analysis in the tank.

키워드

과제정보

연구 과제 주관 기관 : 한국방사선안전재단, 한국연구재단

참고문헌

  1. Fan, H.Z., Aboud, R., Neal P. and Nitheanandan, T.: "Enhancement of the Moderator Subcooling margin using Glass-peened Calandria tube in CANDU reactors", Proceedings of 3 0th CNS Conference, Calgary, Alberta, Canada, May 31-June 3, (2009).
  2. Huget, R.G., Szymanski, J.K. and Midvidy, W.I.: "Status of Physical and Numerical Modelling of CANDU Moderator Circulation", Proceedings of 10th Annual Conference of the Canadian Nuclear Society, Ottawa, (1989).
  3. Huget, R.G., Szymanski, J.K., Galpin, P.F. and Midvidy, W.I.: MODTURC- CLAS: "An Efficient Code for Analyses of Moderator Circulation in CANDU Reactors", Third International Conference on Simulation Methods in Nuclear Engineering, Montreal, Quebec, April 18-20, (1990).
  4. Khartabil, H.F., Khartabil, W.W.R. Inch, Szymanski, J., Novog, D., Tavasoli, V. and Mackinnon, J.: "Three- Dimensional Moderator Circulation Experimental Program for Validation of CFD Code MODTURC_CLAS", Proceedings 21-st Nuclear Simulation Symposium, Ottawa, Canada, Sep. 24-26, (2000).
  5. Hadaller, G.I. et al.: "Frictional Pressure Drop for Staggered and In Line Tube Bank with Large Pitch to Diameter Ratio", Proceedings of 17th CNS Conference, Federiction, New Brunswick, Canada, June 9-12, (1996).
  6. Yoon, C. et al.: "Development and Validation of the 3-D Computational Fluid Dynamics Model for CANDU-6 Moderator Temperature Predictions", Nuclear Technology, vol.148, p.259-267, (2004). https://doi.org/10.13182/NT04-A3565
  7. Yoon, C. et al.: "Moderator Analysis of Wolsong Units 2/3/4 for the 35% Reactor Inlet Header Break with a Loss of Emergency Core Cooling Injection", Journal of Nuclear Science and Technology, Vol. 43, No. 5, p.505-513, (2006). https://doi.org/10.1080/18811248.2006.9711129
  8. Lee, J.R., Yoon, H.Y., Kim, H.T., Jeong, J.J.: "Development Moderator Temperature Prediction by using Porous Media Approach", Proceedings of ICONE20, Anaheim, CA, USA, (2012).
  9. Park, S.G., Lee, J.R., Yoon, H.Y., Kim, H.T., Jeong, J.J.: "Preliminary Analysis of the CANDU Moderator Thermal-Hydraulics using the CUPID Code", Journal of Energy Engineering, Vol. 21, No. 4, pp. 331-337, (2012).
  10. Park, S.K., Jeong, J.J., Lee, J.R., Yoon, H.Y., Kim H.T.: "Assessment of the CUPID code applicability to the thermal-hydraulic analysis of a CANDU moderator system", Progress in Nuclear Energy 75, p.72-79, (2014).
  11. Jeong, J.J., Yoon, H.Y., Park, I.K., Cho, H.K., Lee, H.D.: "Development and preliminary access of a three-dimensional thermal hydraulic code, CUPID", Nuclear Engineering AND Technology, Vol.42, No.3, pp.279-296, (2010). https://doi.org/10.5516/NET.2010.42.3.279
  12. Jeong, J.J., Yoon, H.Y., Park, I.K., Cho, H.K.: "The CUPID Code Development and Assessment Strategy", Nuclear Engineering AND Technology, Vol.42, No.6, pp.636-655, (2010). https://doi.org/10.5516/NET.2010.42.6.636
  13. Yoon, H.Y. et al.: "CUPID Code Manual Volume I: Mathematical Models and Solution Methods", KAERI/TR-4403/2011, KAERI, (2011).
  14. Tentner, A. et al.: "Computational Fluid Dynamics Modeling of Two-Phase Flow Topologies in a Boiling Water Reactor Fuel Assembly", Proceedings of ICONE16, Orlando, USA, (2008).
  15. Lee, J.R., "Numerical Study of Heavy-Water Moderator System with CUPID", KAERI/TR-4509/2011, Korea Atomic Energy Research Institute, (2011).
  16. Yoon, C., Park, J.H.: "Simulation of the Internal Flows of an Inlet Diffuser Assembly for the CANDU-6 Moderator Analysis", Nuclear Technology, vol. 160, pp.314-324, (2007). https://doi.org/10.13182/NT07-A3902
  17. 김형태: "MODTURC_CLAS 코드를 이용한 감속재 3차원 열유동해석", KAERI/TR-3703/2008, Korea Atomic Energy Research Institute, (2008).
  18. Kim, H.T., personal communication, (2014).
  19. Lee, J.R., Park, S.K., Yoon, H.Y., Kim, H.T., Jeong J.J.: "Numerical Study for CANDU Moderator Temperature Prediction by using the Two-Phase Flow Analysis Code, CUPID", Annals of Nuclear Energy 59, 139-148, (2013). https://doi.org/10.1016/j.anucene.2013.04.002