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Numerical Analysis of Single Phase Thermal Stratification in both Cold Legs and Downcomer by Emergency Core Cooling System Injection : A Study on the Necessity to Consider Buoyancy Force Term

비상노심냉각계통 주입에 따른 저온관 및 강수관에서 단상 열성층 수치해석 : 부력항 고려 필요성에 관한 연구

  • Lee, Gong Hee (Nuclear Safety Research Department, Korea Institute of Nuclear Safety) ;
  • Cheong, Ae Ju (Nuclear Safety Research Department, Korea Institute of Nuclear Safety)
  • 이공희 (한국원자력안전기술원 원자력안전연구실) ;
  • 정애주 (한국원자력안전기술원 원자력안전연구실)
  • Received : 2017.09.10
  • Accepted : 2017.10.17
  • Published : 2017.12.10

Abstract

When emergency core cooling system (ECCS) is operated during loss of coolant accident (LOCA) in a pressurized water reactor (PWR), pressurized thermal shock (PTS) phenomenon can occur as cooling water is injected into a cold leg, mixed with hot primary coolant, and then entrained into a reactor vessel. Insufficient flow mixing may cause temperature stratification and steam condensation. In addition, flow vibration may cause thermal stresses in surrounding structures. This will reduce the life of the reactor vessel. Due to the importance of PTS phenomenon, in this study, calculation was performed for Test 1 among six types of OECD/NEA ROSA tests with ANSYS CFX R.17. Predicted results were then compared to measured data. Additionally, because temperature difference between the hot coolant at the inlet of the cold leg and the cold cooling water at the inlet of the ECCS injection line is 200 K or more, buoyancy force due to density difference might have significant effect on thermal-hydraulic characteristics of flow. Therefore, in this study, the necessity to include buoyancy force term in governing equations for accurate prediction of single phase thermal stratification in both cold legs and downcomer by ECCS injection was numerically studied.

Keywords

References

  1. Farkas, T. and Toth, I., 2010, Fluent Analysis of a ROSA Cold Leg Stratification Test, Nuclear Engineering and Design, Vol. 240, pp. 2169-2175. https://doi.org/10.1016/j.nucengdes.2009.11.025
  2. Scheuerer, M. and Weis, J., 2012, Transient Computational Fluid Dynamics Analysis of Emergency Core Cooling Injection at Natural Circulation Conditions, Nuclear Engineering and Design, Vol. 253, pp. 343-350. https://doi.org/10.1016/j.nucengdes.2011.08.063
  3. Sharabi, M., Gonzalez-Albuixech, V. F., Lafferty, N., Niceno, B., and Niffenegger, M., 2016, Computational Fluid Dynamics Study of Pressurized Thermal Shock Phenomena in the Reactor Pressure Vessel, Nuclear Engineering and Design, Vol. 299, pp. 136-145. https://doi.org/10.1016/j.nucengdes.2015.10.014
  4. Nakamura, H., Watanabe, T., Takeda, T., Maruyama, Y., and Suzuki, M., 2009, Overview of Recent Efforts through ROSA/LSTF Experiments, Nuclear Engineering and Technology, Vol. 41, No. 6, pp. 753-764. https://doi.org/10.5516/NET.2009.41.6.753
  5. Japan Atomic Energy Agency, 2008, Final Data Report of OECD/NEA ROSA Project Test 1-1.
  6. Nuclear Energy Agency Committee on the Safety of Nuclear Installations, 2013, Final Integration Report of the OECD/NEA ROSA Project, NEA/CSNI/R(2013)1.
  7. ANSYS CFX, Release 17, ANSYS Inc.
  8. ANSYS CFX-Solver theory guide, ANSYS Inc.
  9. Wagner, W. and Kruse, A., 1998, The Industrial Standard IAPWS-IF97 : Properties of Water and Steam, Springer-Verlag, Berlin.
  10. Menter, F., 2001, CFD Best Practice Guidelines for CFD Code Validation for Reactor Safety Applications, ECORA CONTRACT N$^{\circ}$ FIKS-CT-2001-00154.