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Technical Paper

Effect of Heat Flux on the Concentration Factor in Crevices of Nuclear Steam Generators

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Pages 378-383 | Published online: 13 May 2017

References

  • N. J. CURLEE, Jr. and A. J. BAUM, “Single-Tube Thermal and Hydraulic Tube Support Test,” Vol. 1, EPRI NP-2046, Electric Power Research Institute (Sep. 1981).
  • R. GARNSEY, “Corrosion of Steam Generators,” Nucl. Energy, 18, 117 (1979).
  • P. U. BALAKRISHNAN, “Effect of Condenser Water In-Leakage on Steam Generator Water Chemistry,” AECL-5849, Chalk River Nuclear Laboratories (Jan. 1978).
  • A. E. BERGLES and W. M. ROHSENOW, “The Determination of Forced Convection Surface Boiling Heat Transfer,” 63-HT-22, American Society of Mechanical Engineers (1963).
  • A. H. P. SKELLAND, Diffusional Mass Transfer, p. 68, John Wiley & Sons, New York (1974).
  • J. BROWN, F. GONZALEZ, D. ILEY, and A. McKAY, “Studies of Denting of Steam Generators with Simulated Fresh Water In-Leakage,” Nucl. Technol., 55, 513 (1981).
  • R. S. PATHANIA and E. G. McVEY, “Evaluation of Sodium Phosphate as a Denting Inhibitor,” Nucl. Technol., 55, 178 (1981).

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