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Technical Paper

Pump Behavior and Its Impact on a Loss-of-Coolant Accident in a Pressurized Water Reactor

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Pages 268-277 | Published online: 13 May 2017

REFERENCES

  • “Review and Analysis of State-of-the-Art of Multiphase Pump Technology,” EPRI NP-159, Technical Report 1, Electric Power Research Institute (1976).
  • Idaho National Engineering Laboratory, “RELAP4/MOD5, A Computer Program for Transient Thermal-Hydraulic Analysis of Nuclear Reactors and Related Systems User’s Manual,” ANCR-NUREG-1335, Vol. I, U.S. Nuclear Regulatory Commission (Sep. 1976).
  • D. J. OLSON, “Experiment Data Report for Single and Two-Phase Steady-State Tests of the 1^-Loop Mod-1 Semiscale System Pump,” UC-78, Aerojet Nuclear Company (May 1974).
  • “Pump Two-Phase Performance Program,” EPRINP-1556, Vols. 1 through 8, Project 301, Electric Power Research Institute (Sep. 1980).

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