Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지

Numerical Analysis for Unsteady Thermal Stratified Turbulent Flow in a Horizontal Circular Cylinder

  • Published : 1996.08.01
Download PDF
⟨ Previous Next ⟩

Abstract

In this paper, the unsteady 2-dimensional turbulent flow model for thermal stratification in a pressurizer surge line of PWR plant is proposed to numerically investigate the heat transfer and flow characteristics. The turbulence model is adapted to the low Reynolds number K-$\varepsilon$ model (Davidson model). The dimensionless governing equations are solved by using the SIMPLE (Semi-Implicit Method for Pressure Linked Equations) algorithm. The results are compared with simulated experimental results of TEMR Test. The time-dependent temperature profiles in the fluid and pipe nil are shown with the thermal stratification occurring in the horizontal section of the pipe. The corresponding thermal stresses are also presented. The numerical result for thermal stratification by the outsurge during heatup operation of PWR shows that the maximum dimensionless temperature difference is about 0.83 between hot and cold sections of pipe well and the maximum thermal stress is calculated about 322MPa at the dimensionless time 28.5 under given conditions.

Keywords

References

  1. ASME B 31.1 and Sec. II(Edition)
  2. ASTM A376/A376M-91a
  3. Numerical Heat Transfer v.18 Calculation of thel Turbulent Buoyancy-Driven Flow in a Rectangular Cavity Using an Efficient Solver and Two Different Low Reynolds Number K-ε Turbulence models Davidson, L
  4. Nuclear Engineering and Design v.107 An one dimensional model for the prediction of stratification in horizontal pipes subjected to fluid temperature transient at inlet ; Part 1 : Hydrodynamic model and Part 2 : Thermal model Dhir, V. K;Amar, R. C;Mills, J. C
  5. Nuclear Engineering and Design v.153 Stress analysis of a 900 MW pressurizer surge line including stratification effect Ensel, C;Colas, A;Barthez
  6. Ph. D. thesis, Univ. of Delaware Laminar and Turbulent Natural convection Heat Transfer from Horizontal Cylinder Farouk, B.
  7. ASME paper, No 80-HT-68 Application of K-ε Turbulence Model to an Enclosure Buoyance Driven Recirculation Flow Fraikin, M. P;Portier, J. J;Fraikin, C. T
  8. Journal of Pressure Vessel Technology v.116 Prediction of fluid temperatures from measurements of outside wall temperatures in pipe Guyette, M
  9. Nuclear Engineering and Design v.139 Thermal stratification and reactor piping integrity Kim, J. H;ridt, R. M;Deardorff, A. F
  10. Computer Methods in Applied Mechanics and Engineering v.3 The Numerical computation of Turbulent Flows Launder, B. E;Spalding, D. B
  11. Bulletin No. 88~08 Thermal stress in piping connected to RCS NRC
  12. Bulletin No. 88~11 Pressurizer surge line thermal stratification NRC
  13. Numerical heat transfer and fluid flow Patankar, S. V
  14. NUREG/CR-4731EGG-2469 v.1 Residual life assesment of major light water reactor components-Overview Shah, V. N;MacDonald, P. E
  15. Nuclear Engineering and Design v.18 Result of thermal stratification test in a horizontal pipe line at the HDR-facility Talja, A;Hansjosten, E
  16. J. of Hydraulic Research v.25 no.2 Observation and numerical modelling of density currents resulting from thermal transients in a non rectilinear pipe Viollet, P. L
  17. Nuclear Engineering and Design v.137 Result of HDR-Experiments for pipe load under thermally stratified flow conditions Wolf, L;Hafner, W;Geiss, ;Hansjosten, E;Katzenmeier, G