Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Evaluation of the TEXAS-V Fragmentation Models Against Experimental Data

  • Song Jin H. (Korea Atomic Energy Research Institute) ;
  • Park Ik K. (Korea Atomic Energy Research Institute) ;
  • Nilsuwankosit Sunchai (Department of Nuclear Technology, Faculty of Engineering, Chulalongkorn University)
  • Published : 2004.06.01
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Abstract

This paper presents the results of the TEXAS-V computer code simulations of FARO L-14, L-28, and L-33. The old break-up model and new break-up model are tested to compare the respective simulations of each. As these experimental data sets cover a wide range of ambient pressures, sub-cooling of the water pool, and the melt jet diameters, the results of the simulations will be beneficial in assessing the TEXAS-V code's capability to predict the steam explosion phenomena in a prototypical reactor case. The current model was found to have some deficiencies, and the modules for the fragmentation, the equation of state, and the interfacial area for each flow regime in TEXAS-V were improved for the simulation of FARO L28 and FARO L-33.

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References

  1. Magallon et. al, 2001, Proposal for a OECD research programme on fuel-coolant interaction-Steam Explosion Resolution for Nuclear Applications (SERENA)
  2. J. H. Song et. al., Spontaneous steam explosions observed in the fuel coolant interaction experiments using reactor materials, Journal of Korean Nuclear Society, Vol. 33(4), 344-357, 2002
  3. J. H. Song et. al., Fuel coolant interaction experiments in TROI using a UO2/ZrO2 mixture, Nuclear Engineering and Design, 222, pp.1-15, 2003 https://doi.org/10.1016/S0029-5493(02)00388-6
  4. Chu, C. C., 1986, One-Dimensional Transient Fluid Model for Fuel-Coolant Interaction Analysis, PhD Thesis, University of Wisconsin
  5. Corradini, M. L., El-Beshbeeshy, Nilsuwankosit, S., Tang, J., Fuel Fragmentation model advances using TEXAS-V, 1997, Proceedings of the OECD/CSNI specialists meeting on fuelcoolant interactions, pp.733-738, Tokai Mura, Japan
  6. Annunziato, A., Addabbo, A., Leva, G., 1996, OECD/CSNI international standard problem No. 39 on FARO test L-14, Technical Note No. 1.96.64, Joint Research Center
  7. Annunziato, A., Addabbo, A., Magallon, D., 1999, FARO test L-28 quick look report, Tchnical Note 1.99.74, Joint Research Center
  8. Annunziato, A., Addabbo, A., Magallon, D., 2000, FARO test L-33 quick look report, Tchnical Note I.00.111, Joint Research Center
  9. Chu, C., C. et al, 1984, A Dynamic Model for Droplet Fragmentation, Trans. of Amer. Nuclear Society, V47, Washington, DC.
  10. Young, M. F., 1982, The TEXAS Code for Fuel-Coolant Interaction Analysis, Proc. ANS/ENS LMFBR Safety Topical Mtg., Lyon-Ecully, France
  11. Tang, J., Corradini, M., L., 1996, Final Technical Report for Fuel-Coolant Interaction Analysis for FARO-LWR Test Interpretation, Nuclear Engineering and Engineering Physics, University of Wisconsin
  12. Epstein, M., Fauske , H., K., 1985, Steam Film Instability and the Mixing of Core Melt Jets and Water, Proceedings of National Heat Transfer Conference, Denver, Colorado, USA
  13. Chu, C., C. et. aI., 1995, Ex-Vessel Melt-Coolant Interactions in Deep Water Pool: Studies and Accident Management for Swedish BWRs, Nuclear Engineering Design, vol. 155, p 159-213 https://doi.org/10.1016/0029-5493(94)00874-X