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Technical Paper

Steam-Water Mixing in Nuclear Reactor Safety Loss-of-Coolant Experiments

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Pages 340-343 | Published online: 10 May 2017

References

  • H. C. ROBINSON, “LOFT System and Test Description (Loss-of-Coolant Experiments Using a Core Simulator),” TREE-NUREG-1019, U.S. Nuclear Regulatory Commission (Nov. 1976).
  • S. A. NAFF and P. A. PINSON, “1½ Loop Isothermal Test Program—Program and System Description in Support of Experiment Data Reports,” ANCR-1143, Aerojet Nuclear Company (Feb. 1974).
  • K. R. KATSMA et al., “RELAP4/MOD5-A Computer Program for Transient Thermal-Hydraulic Analysis of Nuclear Reactors and Related Systems—User's Manual,” ANCR-NUREG-1335, Aerojet Nuclear Company (Sep. 1976).
  • D. H. CARD, Ed., “Quarterly Technical Progress Report on Water Reactor Safety Programs Sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, April-June 1977,” TREE-NUREG-1147, pp. II-4–II-10, U.S. Nuclear Regulatory Commission (Aug. 1977).
  • W. H. CRUSH and H. L. O. HOLMSTROM, “Posttest RELAP4 Analysis of LOFT Experiment L1-4,” TREE-NUREG-1183, U.S. Nuclear Regulatory Commission (Nov. 1977).
  • S. F. ZENDER et al., “Experiment Data Report for Semi-scale Mod-1 Tests S-01-4 and S-01-4A (Isothermal Blowdown with Core Resistance Simulator),” ANCR-1196, Aerojet Nuclear Company (Mar. 1975).
  • J. C. VIGIL et al., “Methods, Models, Users Information, and Programming Details,” TRAC-P1: An Advanced Best Estimate Computer Program for PWR LOCA Analysis, Vol. 1, NUREG/CR-0063 LA-7279-MS, Los Alamos Scientific Laboratory (June 1978).

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