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Thermal-Hydraulic Uncertainty Analysis in the Context of Pressurized Thermal Shock Risk Scenarios

  • Y. H. Chang
  • K. Almenas
  • A. Mosleh
  • D. Bessette
Conference paper

Abstract

One of the factors in the decision to extend operating licenses of the United States pressurized reactor reactors (PWRs) is complying with the Pressurized Thermal Shock (PTS) rule, 10CFR50.61, promulgated in 1985. Currently there are ten plants in the United State whose life extension could be affected by the PTS rule. In 1998 the US Nuclear Regulatory Commission (NRC) lunched a PTS re-evaluation project aiming not only reassessing the PTS screening criteria but also taking all important uncertainties into account explicitly. Four PWRs are included in the study: Oconee-1, Beaver Valley-1, Palisades, and Claver Cliffs-1.

Keywords

Primary System Heat Transfor Coefficient Reactor Pressure Vessel Nuclear Regulatory Commission Representative Scenario 
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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References

  1. 1.
    Boyd, C.F. and Dickson, T., Impact of the Heat Transfer Coefficient on Pressurized Thermal Shock. NUREG-1667, 1999, U.S. Nuclear Regulatory Commission.Google Scholar
  2. 2.
    Chang, Y.H., Almenas, K., Mosleh, A., and Pour Gol Mohammad, M., Thermal-Hydraulic Uncertainty Analysis in Pressurized Thermal Shock Risk Assessment-Methodology and Implementation on Oconee, Beaver Valley, and Palisades Nuclear Power Plants (Draft). NUREGICR-XXXX, 2004, U.S. Nuclear Regulatory Commission: Washington DC.Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Y. H. Chang
    • 1
    • 3
  • K. Almenas
    • 1
  • A. Mosleh
    • 1
  • D. Bessette
    • 2
  1. 1.University of MarylandCollege ParkUSA
  2. 2.US Nuclear Regulatory CommissionUSA
  3. 3.Paul Scherrer InstitutSwitzerland

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