Nuclear Engineering and Technology

  • 제41권8호
  • /
  • Pages.1045-1052
  • /
  • 2009
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

PREDICTION OF FREE SURFACE FLOW ON CONTAINMENT FLOOR USING A SHALLOW WATER EQUATION SOLVER

  • 발행 : 2009.10.31
Download PDF
⟨ Previous Next ⟩

초록

A calculation model is developed to predict the transient free surface flow on the containment floor following a loss-of-coolant accident (LOCA) of pressurized water reactors (PWR) for the use of debris transport evaluation. The model solves the two-dimensional Shallow Water Equation (SWE) using a finite volume method (FVM) with unstructured triangular meshes. The numerical scheme is based on a fully explicit predictor-corrector method to achieve a fast-running capability and numerical accuracy. The Harten-Lax-van Leer (HLL) scheme is used to reserve a shock-capturing capability in determining the convective flux term at the cell interface where the dry-to-wet changing proceeds. An experiment simulating a sudden break of a water reservoir with L-shape open channel is calculated for validation of the present model. It is shown that the present model agrees well with the experiment data, thus it can be justified for the free surface flow with accuracy. From the calculation of flow field over the simplified containment floor of APR1400, the important phenomena of free surface flow including propagations and interactions of waves generated by local water level distribution and reflection with a solid wall are found and the transient flow rates entering the Holdup Volume Tank (HVT) are obtained within a practical computational resource.

키워드

참고문헌

  1. Rao D. V., et al., 2003, “Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance,” NUREG/CR-6808, USNRC, (2003)
  2. Maji A. K., et al., “Experimental Validation of CFD Analyses for Estimating the Transport Fraction of LOCA-Generated Insulation Debris to ECCS sump Screens,” Nuclear Technology, 146, 3, (2004)
  3. Kim J., et al., "Three Dimensional CFD Analysis on Containment Pool Recirculation in ECCS Sump Performance Evaluation," Proc. Korean Nuclear Society, Cheju, Korea, May 10~11, 2007
  4. Lee S. W., et al., “Preliminary CFD Analysis on Debris Transport to ECCS Sump in Recirculation Mode for Kori Unit 3,” Proc. Korean Nuclear Society, Pyungchang, Korea, Oct. 30~31, 2008
  5. Kim J., et al., “Assessment on Recirculation Sump Performance for PWR Equipped with IRWST,” Proc. Korean Nuclear Society, Kyeongju, Korea, May 29~30, 2008
  6. KEPCO, 1997, Standard Safety Analysis Report APR-1400, Seoul, Korea. (1997)
  7. ANSYS, FLUENT6.3 Code Manual, Fluent Inc. (2006)
  8. Lee J. I., et al., “Debris Transport Analysis Related with GSI-191 in Advanced Pressurized Water Reactor Equipped with In-containment Refueling Water Storage Tank”, Proceedings of Experiment and Computational Fluid Dynamics for Nuclear Reactor Safety (XCFD4NRS), Grenoble, France, Sep.10~12, 2008
  9. Gottardi G., et al., “Central Scheme for Two-Dimensional Dam-break Flow Simulation,” Advances in Water Resources, 27 (2004) https://doi.org/10.1016/j.advwatres.2003.12.006
  10. Begnudelli L., et al., “Unstructured Grid Finite-Volume Algorithm for Shallow-Water Flow and Scalar Transport with Wetting and Drying,” ASCE Journal of Hydraulic Engineering, 132, 4 (2006) https://doi.org/10.1061/(ASCE)0733-9429(2006)132:4(371)
  11. Valerio C., et al., “Finite Volume Method for Simulating Extreme Flood Events in Natural Channels,” Journal of Hydraulic Research, 41, 2, (2003) https://doi.org/10.1080/00221680309499959
  12. Bang Y. S., et al., “Transient Flow Field in Containment Floor Following a LOCA of APR-1400,” Proc. Korean Nuclear Society, Pyungchang, Korea, Oct. 30~31, 2008
  13. Harten A., Lax P. D., and van Leer B., “On Upstream Differencing and Godunov-type Schemes for Hyperbolic Conservation Laws,” SIAM Review, 25, 1 (1983) https://doi.org/10.1137/1025002
  14. Rogers B. D., et al., “Godunov-type Adaptive Grid Model of Wave-Current Interaction at Cuspate Beaches,” International Journal for Numerical Methods in Fluids, 46 (2004) https://doi.org/10.1002/fld.760
  15. Zhou J. G., et al., “The Surface Gradient Method for the Treatment of Source Terms in the Shallow-Water Equations,” Journal of Computational Physics, 168 (2001) https://doi.org/10.1006/jcph.2000.6670
  16. American Nuclear Society, “Design Criteria for Protection against the Effects of Compartment Flooding in Light Water Reactor Plants,” ANSI/ANS-56.11, La Grange Park, USA, (1988)
  17. http://www-dinma.univ.trieste.it/nirftc/research/easymesh/easymesh.html