References
- D.H. Hwang, et al., Development of a rod bundle correction method and its application to predicting CHF in rod bundles, Nucl. Engrg. & Des. 139, 205-220 (1993) https://doi.org/10.1016/0029-5493(93)90157-5
- J. Weisman, Methods for detaile d thermal and hydraulic analysis of water-cooled reactors, Nucl. Sci. & Engrg., 57, 255-276 (1975)
- P.G. Barnett, An investigation into the validity of certain hypotheses implied by various burnout correlation, U.K. AEA report, AEEW-R214 (1963)
- 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, BNWL-1962, (1976)
- L.S. Tong, An evaluation of the departure from nucleate boiling in bundles of reactor fuel rods, Nucl. Sci. Engrg. 33, 7-15 (1968)
- E.R. Rosal, et al., High pressure rod bundle DNB data with axially non-uniform heat flux, Nucl. Engrg. & Des. 106, 209-220 (1974)
- J. Yates, K. Galbraith, and R. Collingham, DNB and post-DNB heat transfer data in 25 rod bundles, XN-75-54, Exxon Nuclear Corp. 1975, presented at 3rd Water Reactor Satety Information Mtg. Washington, D.C., Sep. (1975)
- D.C. Groeneveld and W.W. Yousef, Springs,Spacing devices for nuclear fuel bundles: A survey of their effect on CHF, Post-CHF heat transfer and pressure drop, ANS/ASME Int. Topl. Mtg. Nuclear reactor thermal-hydraulics, Saratoga, Spring, N.Y., Oct. (1980)
- F. E. Motley, et al., New Westinghouse correlation WRB-1 for predicting critical heat flux in rod bundles with mixing vane grids, Westinghouse report, WCAP-8263, (1976)
- H.B. Giap, et al., A new methodology for developing an empirical DNB correlation
- F.D. Lawrence, et al., Critical Heat Flux in PWR fuel assemblies, AIChE-ASME Heat Transfer Conf.,, Salk Lake City, Utah, Aug. 15-17 (1977)
- J.C.M. Leung and R.E. Henry, Prediction of CHF in rod bundles using round tube CHF correlation, ANS Trans. 33, 963-966 (1979)
- J. Weisman and S.H. Yang, A theoretically based in critical heat flux prediction for rod bundles at PWR conitions, Nucl. Engrg. & Des. 85, 239-250 (1985) https://doi.org/10.1016/0029-5493(85)90289-4
- W.S. Lin, et al., 'Bundle critical power predictions under normal and abnormal conditions in pressurized water reactors, Nucl. Tech. 98, 354-365 (1992)
- K. Rheme, The structure of turbulence in rod bundles and the implications on natural mixing between the subchannels, Int. J. Heat Mass Transfer, 35, 567-581 (1992) https://doi.org/10.1016/0017-9310(92)90291-Y
- F. de Crecy, The effect of grid assembly mixing vanes on critical heat flux value and azimuthal location in fuel assemblies, NURETH-6, Grenoble (1993)
- L.S. Tong, 'Boiling crisis and critical heat flux', U.S. AEC. TID-25887 (1972)
- D.G. Reddy and C.F. Fighetti, Parametric study of CHF data Vol.3: Critical heat flux data, EPRI-NP-2609 (1982)
- D.G. Reddy and C.F. Fighetti, Parametric study of CHF data Vol.2: A generalized subchannel CHF correlation for PWR and BWR fuel assemblies, EPRI-NP-2609, (1982)
- R.V. Macbeth, Burnout analysis, Part 4: Application of a local condition hypothesis to world data for uniformly heated round tubes and rectangular channels, U.K. AEA report, AEEW-R267 (1963)
- SAS user's guide: Statistics, version 5 edition, SAS Institution Inc. (1985)
- L.C. Edwin, et al., Statistics manual, Dover Publications Inc., New York (1956)
- F.H. Bowditch and D.J. Mogford, 'An experimental and analytical study of fluid flow and critical heat flux in PWR fuel elements,' UKAEA report: AEEW-R2050 (1987)
- Vogel, Mixing input data for SIEMENS test sections used by MIX84 code until 1989, KWU B123/1989/e377 (1989)