Advertisement

ATWS Parameter Studies for a Tight-Lattice PWR

  • H. Amm
  • G. Frei
  • M. Dalle Donne
  • J. M. Kallfelz
  • H. Küsters

Abstract

The ATWS behaviour of a tight-lattice (high converter) PWR core in a Kraftwerk Union PWR system is investigated. ATWS results are given for a parameter study of tight-lattice core performance variables which differ appreciably from those of a standard PWR, e. g. the moderator density coefficient, the Doppler coefficient, and the soluble boron worth. For the more favorable of the moderator density coefficient cases considered, the allowable limit for the coolant pressure is not exceeded. For a less favorable density coefficient, coolant pressure is maintained below the allowable limit by increasing the pressurizer relief capacity. To insure reactor shutdown capability, an appreciable increase in the soluble boron concentration of the water injected by the safety systems is necessary.

Keywords

Boron Concentration Allowable Limit Safety Valve Pressurize Water Reactor 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.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. 1.
    H. Küsters, Recent Reactor Physics and Shielding Investigations in the Federal Republic of Germany, in “1980 Advances in Reactor Physics and Shielding,” American Nuclear Society, La Grange Park, II., (1980).Google Scholar
  2. 2.
    V. O. Uotinen, W. L. Bloomfield, M. A. Haghi, H. M. Jones, J. H. Jones, E. C. Toops, M. C. Edlund and R. J. Florian, “Technical Feasibility of a Pressurized Water Reactor Design with a Low Water Volume Fraction Lattice,” EPRI-NP-1833, Electric Power Research Institute, Palo Alto, CA, (May 1981).Google Scholar
  3. 3.
    W. Oldekop, H.-D. Berger and W. Zeggel, General Features of Advanced Pressurized Water Reactors with Improved Fuel Utilization, Nuclear Technology 59:212 (1982).Google Scholar
  4. 4.
    M. Dalle Donne and W. Hame, “A Parametric Thermohydraulic Study of an Advanced Pressurized Light Water Reactor with a Tight Fuel Rod Lattice,” KfK-3453, EUR 7059e, Kernforschungszentrum Karlsruhe, (1982).Google Scholar
  5. 5.
    J.-P. Millot, “Considerations sur les Réacteurs PWR Sous-Modérés,” RGN-Actualités, 1982, No. 4:405, (July-August 1982).Google Scholar
  6. 6.
    R. Chawla, K. Gmür, H. Hager, E. Hettergott, J. M. Paratte, R. Seiler and D. Stahel, Comparisons of Calculated and Measured Parameters for a Pu-Fuelled LWHCR Lattice, “Proc. ANS Topical Meeting on Advances in Reactor Physics and Core Thermal Hydraulics, Kiamesha Lake, N.Y., Sept. 22-24, 1982,” NUREG/CP-0034, U.S. Nuclear Regulatory Commission (1982).Google Scholar
  7. 7.
    B. Kuczera and H. Küsters, Wege zu einem Fortgeschrittenen Druckwasserreaktor (FDWR), KfK Nachrichten 14, 1:34, Kernforschungszentrum Karlsruhe, (Jan. 1982).Google Scholar
  8. 8.
    C. H. M. Broeders, Design-Einflüsse auf einige neutronenphysikalische Eigenschaften eines Fortschrittlichen Druckwasser Reaktors, in “Proc. Jahrestagung Kerntechnik ′83,” Deutsches Atomforum, Bonn (1983).Google Scholar
  9. 9.
    A. C. Thadani and E. W. Hagen, Anticipated Transients Without Scram for Light-Water Reactors, Nucl. Safety 20:422 (July-August 1979).Google Scholar
  10. 10.
    H. Amm and J. M. Kallfelz, ATWS-Prameterstudie fur einen homogenen, engen Gitter DWR (FDWR), INR-1265, Kernforschungszentrum Karlsruhe, (June 1983).Google Scholar
  11. 11.
    C. R. Weisbin, R. W. Peele, J. H. Marable, P. Collins, E. Kujawski, E. Greenspan and G. de Saussure, Sensitivity and Uncertainty Analysis of Reactor Performance Parameters, in “Advances in Nuclear Science and Technology”, Vol. 14, J. Lewins and M. Becker, eds., Plenum Publishing Co., New York, (1982).Google Scholar
  12. 12.
    C. H. M. Broeders, J. M. Kallfelz and H. Küsters, Some Physics and Safety Aspects of a Tight-Lattice PWR, Trans Am. Nucl. Soc. 45, (1983).Google Scholar

Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • H. Amm
    • 1
  • G. Frei
    • 1
  • M. Dalle Donne
    • 2
  • J. M. Kallfelz
    • 2
    • 3
  • H. Küsters
    • 2
  1. 1.Kraftwerk Union AGErlangenFed. Rep. Germany
  2. 2.Kernforschungszentrum KarlsruheKarlsruheFed. Rep. Germany
  3. 3.Georgia Institute of TechnologyAtlantaUSA

Personalised recommendations