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Technical Paper

An Improved Model for Assessing the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors

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Pages 221-233 | Published online: 10 Apr 2017

References

  • M. E. INDIG and J. E. WEBER, “Effects of H2 Additions on Stress Corrosion Cracking in a Boiling Water Reactor,” Corrosion, 41, 19 (1985).
  • E. IBE et al., “Theoretical Model Analyses for Effects of Hydrogen Injection on Radiolysis of Coolant Water in BWR,” J. Nucl. Sci. Technol., 23, 11 (1986).
  • K. ISHIGURE et al., “Hydrogen Injection in BWR and Related Radiation Chemistry,” Radiat. Phys. Chem., 29, 195 (1987).
  • C. P. RUIZ et al., “Modeling Hydrogen Water Chemistry for BWR Applications,” EPRI NP-6386, Electric Power Research Institute (1989).
  • S. R. LUKAC, “Modeling of Radiolysis of Reactor Cooling Water—A Comparative Study,” Radiat. Phys. Chem., 33, 223 (1989).
  • J. CHUN, “Modeling of BWR Water Chemistry,” Master Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology (1990).
  • T. K. YEH, D. D. MACDONALD, and A. T. MOTTA, “Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits—I: The DAMAGE-PREDICTOR Algorithm,” Nucl. Sci. Eng., 121, 468 (1995).
  • T. K. YEH et al., “The Effect of Catalytic Coatings on IGSCC Mitigation for Boiling Water Reactors Operated under Hydrogen Water Chemistry,” Proc. 8th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems— Water Reactors, Amelia Island, Florida, August 10–14, 1997, p. 551 (1997).
  • T. K. YEH et al., “A Comparative Study of the Effectiveness of Hydrogen Water Chemistry by Computer Modeling for Chinshan and Kuosheng,” Proc. 8th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Amelia Island, Florida, August 10–14, 1997, p. 559 (1997).
  • D. D. MACDONALD, “Viability of Hydrogen Water Chemistry for Protecting In-Vessel Components of Boiling Water Reactors,” Corrosion, 48, 194 (1992).
  • D. D. MACDONALD et al., “Theoretical Estimation of Crack Growth Rates in Type 304 Stainless Steel in BWR Coolant Environments,” Corrosion, 52, 768 (1996).
  • A. J. ELLIOT, “Rates Constants and G-Values for the Simulation of the Radiolysis of Light Water Reactor over the Range 0-300°C,” AECL-11073, Atomic Energy of Canada Limited (1994).
  • C. C. LIN et al., “Decomposition of Hydrogen-Peroxide in Aqueous-Solutions at Elevated-Temperatures,” Int. J. Chemical Kinetics, 23, 971 (1991).
  • T. K. YEH and D. D. MACDONALD, “Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuit—II: Simulation of Operating Reactors,” Nucl. Sci. Eng., 123, 295 (1996).
  • T. K. YEH et al., “Predictions of Vessel Internals Susceptible to Irradiation-Induced Degradation for Light Water Reactors Part I. Pressurized Water Reactors,” Nucl. Sci. J., 37, 46 (2000).
  • D. D. MACDONALD, “Calculation of Corrosion Potentials in Boiling Water Reactors,” Proc. 5th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems— Water Reactors, Monterey, California, August 25–29, 1991, p. 935 (1991).
  • T. K. YEH and M. S. YU, “ECP Responses of Platinum Coated Type 304 Stainless Steels to Simulated BWR Environments,” Proc. Int. Conf. Water Chemistry in Nuclear Power Plants, Kashiwazaki, Japan, October 13–16, 1998, p. 180, Japan Atomic Industrial Forum (1998).
  • W. A. STEIN, “A New Equation for Heat and Mass Transfer in Pipe Flow—Part 2,” Int. Chem. Eng., 32, 439 (1992).
  • L. W. NIEDRACH, “Effect of Palladium Coatings on the Corrosion Potential of Stainless Steel in High-Temperature Water Containing Dissolved Hydrogen and Oxygen,” Corrosion, 47, 162 (1991).
  • J. B. LEE, “Electrochemical Approach to Corrosion Problems of Several Iron-Nickel-Chromium Alloys in High Temperature, High Pressure Water,” PhD Thesis, Ohio State University (1978).
  • D. D. MACDONALD et al., “Apparatus for Controlled Hydrodynamic Electrochemical and Corrosion Studies in High-Temperature Aqueous Systems,” Corrosion, 44, 186 (1988).
  • D. D. MACDONALD and M. URQUIDI-MACDONALD, “Thin-Layer Mixed-Potential Model for the Corrosion of High-Level Nuclear Waste Canisters,” Corrosion, 46, 380 (1990).
  • D. D. MACDONALD and M. URQUIDI-MACDONALD, “A Coupled Environment Model for Stress Corrosion Cracking in Sensitized Type 304 Stainless Steel in LWR Environments,” Corrosion Sci., 32, 51 (1991).
  • “Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors,” Generic Letter 94-03, U.S. Nuclear Regulatory Commission (1994).
  • “Cracking in the Lower Region of the Core Shroud in Boiling Water Reactors,” Information Notice 94-42, U.S. Nuclear Regulatory Commission (1994).
  • “Reactor Vessel Top Guide and Core Plate Cracking,” Information Notice 95-17, U.S. Nuclear Regulatory Commission (1995).
  • T. K. YEH and M. S. YU, “An Overview of Vessel Internals Degradation in Boiling Water Reactors,” INER Quarterly, 23, 48 (1997).

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