COMPARISON OF DRYOUT POWER DATA BETWEEN CANFLEX MK-V AND CANFLEX MK-IV BUNDLE STRINGS IN UNCREPT AND CREPT CHANNELS

  • JUN JI SU (Korea Atomic Energy Research Institute) ;
  • LEUNG L.K.H. (Atomic Energy of canada Limited Chalk River)
  • Published : 2005.12.01

Abstract

The CANFLEX Mk-V bundle is designed to improve upon the critical heat flux (CHF) characteristics of the CANFLEX Mk-IV bundle. The main difference between these two bundles is an increase in bearing pad height of about 0.3 mm in the CANFLEX Mk-IV bundle. This change in bearing pad height leads to an increase in gap flow at the bottom of the bundle, primarily eliminating the localized narrow-gap effect that limits the CHF of the CANFLEX Mk-IV bundle. The objective of this paper is to examine the effects of bearing pad height and pressure tube creep on the sheath-temperature distribution, dryout power, and dryout location, as observed ken full-scale bundle tests, between CANFLEX Mk-IV and Mk-V bundles In uncrept and crept channels. A comparison of surface-temperature differences between the top and bottom elements of the bundles showed that increasing the bearing pad height has led to a more homogeneous enthalpy distribution in subchannels of the bundle. Initial dryout locations of the CANFLEX Mk-V bundle were mainly observed at the mid-spacer plane of either the $10^{th}$ (about $80\%$) or $11^{th}$ ($20\%$) bundle in the 12-bundle string, as compared to the mid-spacer and downstream-button planes for the CANFLEX Mk-IV bundle. Dryout power and boiling-length-average (BLA) CHF values exhibit consistent trends and little scatter with varying flow conditions for both types of CANFLEX bundles in uncrept and crept channels. An increase in pressure tube creep has led to a reduction in dryout power (about $20\%$ far the $3.3\%$ crept channel and $27\%$ for the $5.1\%$ crept channel as compared to dryout powers for the uncrept channel). Increasing the bearing pad height of the CANFLEX bundle has led to an increase in the dryout power. Overall, the dryout power of the CANFLEX Mk-V bundle is 7 to $10\%$ higher than that of the CANFLEX Mk-IV bundle at the inlet temperature range of interest (i.e., between 243 and $290^{\circ}C$).

Keywords

References

  1. J.S. Jun, H.C. Suk, M.S. Cho, J.Y. Jung, C.K. Jo and C.J. Jeong, 'The Design Manual of CANFLEX-NU Fuel Bundle for CANDU-6 Reactor', KAERI/TR-2576/2003(internal report), October 2003
  2. W.W.R. Inch, H.C. Suk, 'Demonstration Irradiation of CANFLEX in Pt. Lepreau', IAEA Technical Committee Meeting on Fuel Cycle Options for LWRs and HWRs, Victoria, Canada, April 1998
  3. J.Y. Jung, J.S. Jun, M.S. Cho, H.C. Suk, S.D. Lee and H.B. Seo, 'Evaluation of CANFLEX-NU Fuel Performance Irradiated in Wolsong Generation Station #1 and In-Bay Inspection', Proceedings of the KNS Spring Meeting, Korea, May 2004
  4. G.R. Dimmick, W.W.R. Inch, J.S. Jun, H.C. Suk, G.I. Hadaller, R.A. Fortman and R.C. Hayes, 'Full Scale Water CHF Testing of the CANFLEX Bundle', the 6th International Conference on CANDU Fuel, Canadian Nuclear Society, September 1999
  5. J.S. Jun, H.C. Suk, and J.H. Park, 'The Analysis of Water CHF Test Data of CANFLEX-NU Fuel Bundle', Proceedings of the KNS Spring Meeting, Korea, May 2000
  6. J.S. Jun, H.C. Suk, and J.H. Park, 'The Water CHF Tests of CANFLEX-NU Fuel Bundle in Crept Pressure Tubes', Proceedings of the KNS Spring Meeting, Korea, May 2000
  7. L.K.H. Leung, J.S. Jun, D.E. Bullock, W.W.R. Inch and H.C. Suk, 'Dryout Power in a CANFLEX Bundle String with Raised Bearing Pads', the 7th International Conference on CANDU Fuel, Canadian Nuclear Society, September 2001
  8. R.A. Fortman, G.I. Hadaller, R.C. Hayes and F. Stern, 'Heat Transfer Studies with CANDU Fuel Simulators', the 5th International Conference on Nuclear Engineering, ICONE5, 1997 May, Nice, France
  9. L.K.H. Leung, D.C. Groeneveld, G.R. Dimmick, D.E. Bullock, and W.W. Inch, 'Critical Heat Flux and Pressure Drop for a CANFLEX Bundle String Inside an Axially Non-Uniform Flow Channel', Proceedings of the 6th International Conference on CANDU Fuel, Canadian Nuclear Society, September 1999