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Power Reactor Systems

  • Samuel Glasstone
  • Alexander Sesonske
Chapter
  • 736 Downloads

Abstract

13.1. The practice of nuclear engineering is focused on the design and operation principles of commercial nuclear power plants. In previous chapters we have discussed many such principles that apply particularly to light-water reactors (LWRs). A brief overview of pressurized-water (PWR) and boiling-water reactors (BWR) was given in Chapter 1 to provide a general background and the material in subsequent chapters tended to further develop an understanding of such systems.

Keywords

Fuel Assembly Steam Generator Critical Heat Flux Guide Tube Coolant Flow Rate 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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General References

  1. Collier, J. G., and G. F. Hewitt, “Introduction to Nuclear Power,” Hemisphere Publishing Corp., 1987.Google Scholar
  2. Knief, R. A., “Nuclear Engineering, Theory and Technology of Commercial Nuclear Power,” Hemisphere Publishing Corp., 1992.Google Scholar
  3. Nero, A. V., “A Guidebook to Nuclear Reactors,” University of California Press, 1979.Google Scholar
  4. Rahn, F. J., et al., “A Guide to Nuclear Power Technology,” John Wiley & Sons, 1984.Google Scholar

References

  1. 1.
    R. A. Knief, “Nuclear Engineering, Theory and Technology of Commercial Nuclear Power,” Hemisphere Publishing Corp., 1992;Google Scholar
  2. F. J. Rahn et al., “A Guide to Nuclear Power Technology,” John Wiley & Sons, 1984.Google Scholar
  3. 2.
    “Reference Safety Analysis Report, RESAR-41,” Westinghouse Electric Corp., U.S. NRC Report DOCKET-STN-50480–1, 1974.Google Scholar
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    J. J. Duderstadt and L. J. Hamilton, “Nuclear Reactor Analysis,” John Wiley & Sons, 1976, p. 399–405.Google Scholar
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  6. C. W. Bagnal et al., Nucl. Safety, 33, 47 (1992).Google Scholar
  7. 5.
    S. Hoffman and T. Moore, Eds., “General Description of a Boiling Water Reactor,” General Electric Co., 1976.Google Scholar
  8. 6.
    F. J. Rahn et al., “Nuclear Engineering, Theory and Technology of Commercial Nuclear Power,” Hemisphere Publishing Corp., p. 593 et seq.; 1992Google Scholar
  9. G. L. Brooks, “The Standardized CANDU 600,” Atomic Energy of Canada, Ltd., 1974.Google Scholar
  10. 7.
    V. G. Snell et al., Nucl. Safety, 31, 20 (1990).Google Scholar
  11. 8.
    L. Rib et al., “Proc. Topical Meeting on the Next Generation of Nuclear Power Plants,” American Nuclear Society, 1991.Google Scholar

Copyright information

© Springer Science+Business Media Dordrecht 1994

Authors and Affiliations

  • Samuel Glasstone
  • Alexander Sesonske

There are no affiliations available

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