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Technical Paper

Probabilistic Analysis of the Interfacing System Loss-of-Coolant Accident and Implications on Design Decisions

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Pages 5-12 | Published online: 10 May 2017

References

  • Reactor Safety Study, WASH-1400 (NUREG-75/014), U.S. Atomic Energy Commission (Oct. 1975).
  • Standard Review Plan, NUREG-75/087, U.S. Nuclear Regulatory Commission (Sep. 1975).
  • G. H. SANDLER, System Reliability Engineering, Prentice-Hall, Inc., Englewood Cliffs, New Jersey (1963).
  • J. R. KELLY, F. L. LEVERENZ, N. J. McCORMICK, and R. C. ERDMANN, “Sensitivity Assessments in Reactor Safety Analysis,” EPRI 217-2-6, pp. 38–55, Electric Power Research Institute (Feb. 1976).
  • F. L. LEVERENZ, J. E. KELLY, A. A. GARCIA, and R. C. ERDMANN, “PWR Sensitivity to Alterations in the Interfacing Systems LOCA,” EPRI NP-262, Electric Power Research Institute (Sep. 1976).
  • Reactor Safety Study, WASH-1400 (NUREG-75/014), Vol. 5, pp. V-43 through V-44, U.S. Atomic Energy Commission (Oct. 1975).

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