EVALUATION OF METHODOLOGY FOR AXISYMMETRIC SIMULATION OF RCCS IN VHTR

초고온가스로의 RCCS 해석을 위한 축대칭 모사 방법론 평가

  • 김성훈 (한국원자력연구원, 스마트개발본부) ;
  • 조봉현 (한국원자력연구원, 수소생산원자로기술개발부) ;
  • 탁남일 (한국원자력연구원, 수소생산원자로기술개발부) ;
  • 김민환 (한국원자력연구원, 수소생산원자로기술개발부)
  • Received : 2009.06.03
  • Accepted : 2010.03.12
  • Published : 2010.03.31

Abstract

RCCS is a passive safety-related system that removes the decay heat of VHTR when normal decay heat removal systems are in failure. Understanding thermo-hydraulics of RCCS is important to design a safer VHTR. RCCS consists of 292 cooling panels, which are placed in the reactor cavity. The layout of RCCS gives an idea that, for CFD simulations, cooling panels can be assumed to be one annulus tube. This assumption can reduce significantly the computational time, especially for the unsteady simulation. To simulate RCCS in an axisymmetric manner, three models were suggested and compared. Each model has (1) the same outer radius, (2) the same cross-sectional area (3) the same pressure drop, respectively, as the RCCS cooling panels. The steady-state simulation was conducted with these three models and the DO radiation model. It is found that over 90% of the heat from the outer wall of the reactor pressure vessel is transported to the RCCS by radiative heat transfer. The simulation with the third model, which has the same pressure drop as the design, estimates the closest wall temperature profiles to a thermo-hydraulic code, GAMMA+, result.

Keywords

References

  1. 1996, General Atomics, "Gas Turbine-Modular Helium Reactor (GT-MHR) Conceptual Design Description Report," Rev.01.
  2. 2006, Lim, H.S. and No, H.C., "GAMMA multi-dimensional multi-component mixture analysis to predict air ingress phenomena in an HTGR," Nuclear Science and Engineering, Vol.152, pp.87-97.
  3. 2007, Oh, C., No, H.C., Lim, H.S., Kim, E.S. and Kim, J.H., "Development of GAMMA Code and Evaluation for a Very High Temperature Gas-Cooled Reactor," 2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management, Boston, Massachusetts, June.
  4. 2007, No, H.C., Lim, H.S., Kim, J., Oh, C., Siefken, L. and Davis, C., "Multi-component diffusion analysis and assessment of GAMMA code and improved RELAP5 code," Nuclear Engineering and Design, Vol.237, pp.997-1008. https://doi.org/10.1016/j.nucengdes.2006.10.020
  5. 2008, Kim, E.S., No. H.C., Kim, B.J. and Oh, C.H., "Esitmation of graphite density and mechanical strength variation of VHTR during air-ingress accident," Nuclear Engineering and Design, Vol.238, pp.837-847. https://doi.org/10.1016/j.nucengdes.2007.08.002
  6. 2009, Jun, J.S, Lim, H.S., Jo, C.K. and Noh, J.M., "Thermal-Fluid Analysis of the PMR 200MWth Reactor System at the Steady State and Transient Conditions," 2009 Transactions of Korean Nuclear Society Spring Meeting, Jeju, Korea, May.
  7. 2004, van Staden, M.P., "Analysis of Effectiveness of Cavity Cooling System," 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, CHINA, September 22-24.
  8. 2005, Tzanos, C.P., "CFD Analysis for the Applicability of the Natural Convection Shutdown Heat Removal Test Facility (NSTF) for the Simulation of the VHTR RCCS," ANL-GenIV-55, Argonne National Laboratory Report.
  9. 1972, Siegel, R. and Howell, J., Thermal Radiation Heat Transfer, McGraw-Hill, Tokyo, pp.387-389.
  10. 2008, Tak, N., Lim, H.S., Kim, M.H. and Lee, W.J., "Thermal Performance Analysis of a Cooled-Vessel Design Using GAMMA+," Transactions of the Korean Nuclear Society Spring Meeting, Gyeongju, Korea, May.
  11. 2008, 탁남일, "RCCS 2-D FLUENT 해석을 위한 Geometry, 경계조건, 물성자료," Internal communication, 한국원자력연구원.
  12. 1996, Idelchik, I.E., Handbook of Hydraulic Resistance, Begell House, New York, pp.75-121.
  13. 2006, FLUENT, FLUENT User's guide, FLUENT Inc.
  14. 1993, Chui, E.H. and Raithby, G.D., "Computation of Radiant Heat Transfer on a Non-Orthogonal Mesh Using the Finite-Volume Method," Numerical Heat Transfer, Part B, Vol.23, pp.269-288. https://doi.org/10.1080/10407799308914901