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Nuclear Technology Volume 46, 1979 - Issue 3: Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16-19,1978) Part Two
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Technical Paper

Radioactivity Release versus Probability for a Steam Generator Tube Rupture Accident

A. J. BuslikBrookhaven National LaboratoryDepartment of Nuclear Energy, Upton, New York 11973
&
R. E. HallBrookhaven National LaboratoryDepartment of Nuclear Energy, Upton, New York 11973
Pages 566-570 | Published online: 10 May 2017

References

  • Reactor Safety Study, An Assessment of Accident Risks in U.S. Commercial Nuclear Plants, WASH-1400 (NUREG-75/014), U.S. Nuclear Regulatory Commission (Oct. 1975).
  • “The Safety of Nuclear Power Reactors (Light Water-Cooled) and Related Facilities,” WASH-1250, U.S. Atomic Energy Commission (July 1973).
  • RESAR-3S, Westinghouse Electric Corporation (July 1975).
  • “Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code),” NUREG-0017, U.S. Nuclear Regulatory Commission (Apr. 1976).
  • W. F. PASEDAG, “Iodine Spiking in BWR and PWR Coolant Systems,” Proc. ANS Topl. Mtg. Thermal Reactor Safety, July 31-August 4, 1977, Sun Valley, Idaho, CONF-770708, p. 3-217, U.S. Energy Research and Development Administration (1977).
  • K. H. NEEB and E. SCHUSTER, “Iodine Spiking in PWRs: Origin and General Behavior,” Trans. Am. Nucl. Soc., 28, 650 (1978).
  • R. J. LUTZ, Jr., “Iodine Behavior Under Transient Conditions in the Pressurized Water Reactor,” WCAP-8637, Westinghouse Electric Corporation (Nov. 1975).
  • R. J. LUTZ, Jr. and W. CHUBB, “Iodine Spiking-Cause and Effect,” Trans. Am. Nucl. Soc., 28, 649 (1978).
  • G. F. CARUTHERS and R. W. GRITZ, “Radioiodine Behavior During a Steam Generator Tube Rupture Accident,” Trans. Am. Nucl. Soc., 28, 653 (1978).
  • A. K. POSTMA and P. S. TAM, “Iodine Behavior in a PWR Cooling System Following a Postulated Steam Generator Tube Rupture Accident,” BCT-102, Benton City Technology, Benton City, Washington (Nov. 1977).
  • N. EIKELPASCH, R. SEEPOLT, and R. HOCK, “Iodine Release Mechanism and Its Verification in Plant Operation,” Trans. Am. Nucl. Soc., 28, 652 (1978).
  • WCAP-8185, Westinghouse Electric Corporation (1973).
  • H. M. FONTECILLA and B. K. GRIMES, “Radiological Consequences of a Main Steam Line Failure with Large Steam Generator Tube Leaks,” Proc. ANS Topl. Mtg. Thermal Reactor Safety, July 31-August 4, 1977, Sun Valley, Idaho, CONF-770708, p. 3-203, U.S. Energy Research and Development Administration (1977).

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