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Technical Paper

An Evaluation of the Thermal-Hydraulic and Fuel Rod Thermal and Mechanical Deformation Behavior during the First Power Burst Facility Nuclear Blowdown Tests

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Pages 401-410 | Published online: 10 May 2017

References

  • T. F. COOK, “An Evaluation of Fuel Rod Behavior During Test LOC-11,” NUREG/CR-0590, TREE-1328, U.S. Nuclear Regulatory Commission (Mar. 1979).
  • J. R. LARSON et al., “PBF-LOCA Test Series, Test LOC-11 Test Results Report,” NUREG/CR-0618, TRIEE1329, U.S. Nuclear Regulatory Commission (Mar. 1979).
  • S. R. FISCHER et al., “RHLAP4/MOD6-A Computer Program for Transient Thermal-Hydraulic Analysis of Nuclear Reactors and Related Systems-User’s Manual,” CDAP TR003 (Jan. 1978). Available from the National Energy Software Center, Attention Margaret Butler, 9700 South Cass Avenue, Building 203, Room C230, Argonne, Illinois 60439.
  • J. A. DEARIEN et al., “FRAP-T4-A Computer Code for the Transient Analysis of Oxide Fuel Rods,” TFBP-TR-237 (Nov. 1977). Available from the National Energy Software Center, Attention Margaret Butler, 9700 South Cass Avenue, Building 203, Room C230, Argonne, Illinois 60439.
  • L. S. TONG, “Prediction of Departure from Nucleate Boiling for an Axially Non-Uniform Heat Flux Distribution,” J. Nucl. Energy, 21, 241 (1967).
  • R. A. SMITH and P. GRIFFITH, “A Simple Model for Estimating Time to CI IF in a PWR LOCA,” Trans. ASME, Paper No. 76-HT-9, American Society of Mechanical Engineers (1976).
  • J. A. DEARIEN et al., “FRAP-S3: A Computer Code for the Steady State Analysis of Oxide Fuel Rods,” TFBP-TR-164 (Oct. 1977). Available from the National Energy Software Center, Attention Margaret Butler, 9700 South Cass Avenue, Building 203, Room C230, Argonne, Illinois 60439.

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