Open Access
| Issue |
EPJ Nuclear Sci. Technol.
Volume 2, 2016
|
|
|---|---|---|
| Article Number | 16 | |
| Number of page(s) | 10 | |
| DOI | https://doi.org/10.1051/epjn/2016010 | |
| Published online | 01 April 2016 | |
- G.C. Dimmick, W.W.R. Inch, J.S. Jun, H.C. Suk, G.I. Hadaller, R.A. Fortman, R.C. Hayes, Full scale water CHF testing of the CANFLEX bundle, in Proceeding of the 6th International Conference on CANDU fuel , Niagara Falls, Ontario, Canada (1999), pp. 103–113 [Google Scholar]
- J.S. Jun, Thermalhydraulic evaluations for CANFLEX bundle with natural or recycled uranium fuel in the uncrept and crept channels of a CANDU-6 reactor, Nucl. Eng. Technol. 35 , 479 (2005) [Google Scholar]
- L.K.H. Leung, F.C. Diamayuga, Measurements of critical heat flux in CANDU 37-element bundle with a steep variation in radial power profile, Nucl. Eng. Des. 240 , 290 (2010) [CrossRef] [Google Scholar]
- A. Tahir, Y. Parlatan, M. Kwee, W. Liauw, G. Hadaller, R. Fortman, Modified 37-element bundle dryout, in NURETH-14 , Hilton Toronto Hotel, Toronto, Ontario, Canada (2011) [Google Scholar]
- J.H. Park, Y.M. Song, The effect of inner ring modification of standard 37-element fuel on CHF enhancement, Ann. Nucl. Energy 70 , 135 (2014) [CrossRef] [Google Scholar]
- J.H. Park, J.Y. Jung, E.H. Ryu, CHF Enhancement of Advanced 37-element Fuel bundles, Sci. Technol. Nucl. Installations 2015 , 243867 (2015) [Google Scholar]
- M.B. Carver, J.C. Kiteley, R.Q.N. Zou, S.V. Junop, D.S. Rowe, Validation of the ASSERT subchannel code; prediction of critical heat flux in standard and nonstandard CANDU bundle geometries, Nucl. Technol. 112 , 299 (1995) [Google Scholar]
- C.L. Wheeler et al., COBRA-IV-I: an interim version of COBRA for thermal-hydraulic analysis of rod-bundle nuclear fuel elements and cores, Battelle Pacific Northwest Laboratories Report, BNWL-1962, 1976 [Google Scholar]
- C.W. Stewart et al., COBRA-IV: The model and the method, Battelle Pacific Northwest Laboratories Report, BNWL-2214, 1977 [Google Scholar]
- AECL, Fuel Design Manual for CANDU-6 reactors, DM-XX-37000-001, 1989 [Google Scholar]
- D.C. Groeneveld, L.K.H. Leung, P.L. Kirillov, V.P. Bobkov, I.P. Smogalev, V.N. Vinogradov, X.C. Huang, E. Royer, The 1995 look-up table for critical heat flux in tubes, Nucl. Eng. Des. 163 , 1 (1995) [Google Scholar]
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