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Nuclear Technology Volume 154, 2006 - Issue 2
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Technical Paper

The Core Characteristics of a LOCA Power Pulse in a CANDU-6 Reactor with the CANFLEX-RU Fuel

Chang Joon JeongKorea Atomic Energy Research InstituteDry Process Fuel Technology Development Division, P.O. Box 105 Yuseong, Daejeon 305-600, Korea
&
Ho Chun SukKorea Atomic Energy Research InstituteDry Process Fuel Technology Development Division, P.O. Box 105 Yuseong, Daejeon 305-600, Korea
Pages 215-223 | Published online: 10 Apr 2017

References

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  • A. D. LANE, J. GRIFFITHS, and I. J. HASTINGS, “The Role of the New CANFLEX Fuel Bundle in Advanced Fuel Cycles for CANDU Reactors,” Proc. Canadian Nuclear Society 10th Annual Conf., Ottawa, Canada, June 4-7, 1989.
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  • G. KUGLER and A. R. DASTUR, “Accuracy of Improved Quasistatic Space-Time Method Checked with Experiment,” AECL-5533, Atomic Energy of Canada Limited (1976).
  • S. LAM, T. M. KIM, and N. H. LEE, “Analysis Report: Large Loss of Coolant Accident (Large LOCA) Wolsong NPP 2, 3, 4,” 86-03500-AR-029, Korea Atomic Energy Research Institute/Atomic Energy of Canada Limited (1995).
  • “Final Safety Analysis Report Wolsong Nuclear Power Plant Units No. 2, 3, 4,” Korea Electric Power Corporation (1997).

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