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Technical Paper

Test Prediction for the German PKL Test K5A Using RELAP4/MOD6

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Pages 199-204 | Published online: 10 May 2017

References

  • K. V. MOORE and W. H. RETTIG, “RELAP4-A Computer Program for Transient Thermal-Hydraulic Analysis,” ANCR-1127, Aerojet Nuclear Company (Mar. 1975).
  • R. A. NELSON and L. H. SULLIVAN, “RELAP4/MOD6 Reflood Heat Transfer and Data Comparison,” CSNI Specialists' Mtg. Transient Two-Phase Flow, Paris (1978).
  • RELAP4/MOD5: “A Computer Program for Transient Thermal-Hydraulic Analysis of Nuclear Reactors and Related Systems User's Manual Volumes I, II, and III,” ANCR-NUREG-1335, Aerojet Nuclear Company (1976).
  • G. B. WALLIS, One-Dimensional Two-Phase Flow, McGraw-Hill Book Company, New York (1969).
  • W. L. KIRCHNER, “Reflood Heat Transfer in a Light Water Reactor,” PhD Dissertation, Massachusetts Institute of Technology, Cambridge, Massachusetts (1976).
  • R. MANDL, “Reflood Tests with a Consideration of the Primary Loops and Instrumentation of the Test Facility,” KWU Progress Report No. 343/75, Kraftwerk Union (Oct. 1975).
  • H. SCHWEIKERT, “Refilling Tests with Consideration of the Primary Loops, PKL,” KWU Report No. RS 36/2, Kraftwerk Union (Mar. 1975).

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