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Technical Paper

Fuel Channel Analysis for a Large-Break Loss-of-Coolant Accident in a Canada Deuterium Uranium Reactor Loaded with CANFLEX Fuel Bundles

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Pages 292-307 | Published online: 10 May 2017

References

  • A. D. LANE et al., “CANFLEX: A Fuel Bundle to Facilitate the Use of Enrichment and Fuel Cycles in CANDU Reactors”, Proc. Technical Committee Mtg. Advances in Heavy Water Reactors, Toronto, Canada, June 7–10, 1993, International Atomic Energy Agency.
  • D. J. RICHARDS, “Validation of CATHENA Two-Fluid Code,” presented at 3rd Int. Topi. Mtg. Reactor Thermal-hydraulics and Operations, Seoul, Korea, November 14–17, 1988.
  • R. G. MOYER, D. B. SANDERSON, R. W. TIEDE, and H. E. ROSINGER, “Bearing Pad/Pressure Tube Rupture Experiments”, Proc. 13th Annual Conf., Saint John, New Brunswick, Canada, June 7–10, 1992, Canadian Nuclear Society (1992).
  • T. NITHEANANDAN, Q. M. LEI, and R. G. MOYER, “Analysis of Bearing Pad to Pressure Tube Contact Heat Transfer,” Proc. Nuclear Simulation Symp., Pembroke, Ontario, Canada, October 12–14, 1994, p. 274, Canadian Nuclear Society (1994).
  • D. J. OH, S. GIRGIS, A. C. D. WRIGHT, and R. W. HOLMES, “Predictions of Fuel Channel Behaviour for Large LOCA in CANDU Reactors”, Proc. 4th Int. Conf. Simulation Methods in Nuclear Engineering, Montreal, Quebec, June 2–4, 1993, Canadian Nuclear Society (1993).
  • J. GERARDI, “CHF-Enhanced CANDU Fuel Bundles”, Inter-Comm—Atomic Energy of Canada Limited Research Weekly Newsletter, 9, 75, 1, (Oct. 14, 1994).
  • R. S. W. SHEWFELT, L. W. LYALL, and D. P. GODIN, “A High Temperature Creep Model for Zr-2.5 wt% Nb Pressure Tubes”, Nucl. Mater., 125, 228 (1984).
  • R. S. W. SHEWFELT and D. P. GODIN, “Verification Tests for GRAD, A Computer Program to Predict the Non-Uniform Deformation and Failure of Zr-2.5 wt% Nb Pressure Tubes During a Postulated Loss-of-Coolant Accident,” AECL-8384, Atomic Energy of Canada Limited (1985).
  • G. E. GILLESPIE, R. G. MOYER, and P. D. THOMPSON, “Moderator Boiling on the External Surface of a Calandria Tube in a CANDU Reactor During a Loss-of-Coolant Accident,” AECL-7664, Atomic Energy of Canada Limted (1982).

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