Acknowledgement
Supported by : National Research Foundation of Korea (NRF)
References
- T.E. Schaubel, CNSC Staff Reviewof Pickering NGS-B Integrated Safety Review, Safety Analysis Safety Factors Report, 2008.
- G.H. Roh, Y.H. Kim, N.Z. Cho, Improvement of power coefficient by using burnable poison in the CANDU reactor, Nucl. Eng. Design. 241 (2011) 1565-1578. https://doi.org/10.1016/j.nucengdes.2011.01.050
- J.H. Lau, F.J. Doria, H. Chow, L.K.H. Leung, S. Palleck, K.S. Sim, Z. He, P. Purdy, Design and qualification of the Bruce CANFLEX low void reactivity fuel bundle - an overview, Proceedings of the 25th CNS Annual Conference, Toronto, Ontario, June 6-9, 2004.
- M.F. Lightstone, NUCIRC-MOD1.505 User's Manual, TTR-516, Atomic Energy of Canada Limited, 1993.
- J.H. Park, H.B. Choi, M.S. Yang, Progress of the DUPIC fuel compatibility analysis - II. Thermal hydraulics, Nucl. Technol. 153 (2006) 164-174. https://doi.org/10.13182/NT06-A3697
- W.J. Hartmann, NUCIRC Predictions of channel flow and comparison with ste measurements at the Point Lepreau Generating Station, in: Proceedings of the CNS 13th Annual Reactor Simulation Symposium, Chalk River, Ontario, Canada, 1987.
- J.H. Bae, G.H. Roh, J.H. Park, Comparison of fuel temperature characteristics between standard 37 element and CANFLEX fuel bundles, in: Korean Nuclear Society Autumn Meeting, 2010.
- P.G. Boczar, I.J. Hastings, A. Celli, Recycling in CANDU of Uranium and/or Plutonium from Spent LWR Fuel, AECL Report, AECL-10018, 1989.
- R.J. Stamm'ler, J.J. Casal, E.A. Villarino, A.A. Ferri, HELIOS Methods, Studsvik Scanpower, 1998.
- J.H. Bae, J.Y. Jeong, Fuel temperature characteristics for fuel channels using burnable poison in the CANDU reactor, in: Korean Nuclear Society Spring Meeting, 2013.
- L.K.H. Leung, D.C. Groeneveld, G.R. Dimmick, D.E. Bullock, W.W. Inch, Critical heat flux and pressure drop for a CANFLEX bundle string inside an axially non-uniform flow channel, in: Proceedings of the 6th International Conference on CANDU Fuel, Canadian Nuclear Society, 1999.
- J.H. Bae, G.H.Roh, Y.M. Song, Thermal-hydraulic characteristics for fuel channels using burnable poison in the CANDU reactor, in: Korean Nuclear Society Autumn Meeting, 2012.
- L.K.H. Leung, J.S. Jun, D.E. Bullock, W.W. Inch, H.C. Suk, Dryout power in a CANFLEX bundle string with raised bearing pads, in: 7th International Conference on CANDU Fuel, Canadian Nuclear Society, 2001.
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