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Radiation Environments in Nuclear Reactor Power Plant

Post-Loss-of-Coolant Accident Doses to Pressurized Water Reactor Equipment

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Pages 74-78 | Published online: 12 May 2017

References

  • “Preliminary Safety Analysis Report, Perry Nuclear Power Plant,” Docket Number 50-440, The Cleveland Electric Illuminating Company (1973).
  • M. J. KOLAR and N. C. OLSON, “Calculation of Accident Doses to Equipment Inside Containment of Power Reactors,” Nucl. Technol., 36, 56 (1977).
  • “Reactor Safety Study–An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants,” WASH-1400, U.S. Nuclear Regulatory Commission (Oct. 1975).
  • “Calculation of Distance Factors for Power and Test Reactor Sites,” TID-14844, U.S. Nuclear Regulatory Commission (Mar. 1962).
  • “USNRC Standard Review Plan, Section 15.6.5,” NUREG-75/087, U.S. Nuclear Regulatory Commission (Nov. 1975).

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