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Nuclear Technology Volume 46, 1979 - Issue 3: Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16-19,1978) Part Two
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Technical Paper

Thermal-Hydraulic Analysis of Fuel Blockages Formed during Transient Overpower Accidents in Liquid-Metal Fast Breeder Reactors

V. K. DhirUniversity of California, Los Angeles, School of Engineering and Applied Science, Los Angeles, California 90024
,
W. E. KastenbergUniversity of California, Los Angeles, School of Engineering and Applied Science, Los Angeles, California 90024
&
D. W. VarelaUniversity of California, Los Angeles, School of Engineering and Applied Science, Los Angeles, California 90024
Pages 447-452 | Published online: 10 May 2017

References

  • E. T. RUMBLE III, “A Hypothetical Overpower Excursion Model for Liquid Metal-Cooled Fast Breeder Reactors,” PhD Dissertation, University of California, Los Angeles (June 1974).
  • L. L. SMITH et al., “SAS/FCI, A Fuel-Coolant Interaction Model for LMFBR Whole-Core Accident Analysis,” Proc. ANS Topl. Mtg. Mathematical Models and Computation Techniques for Analysis of Nuclear Systems, Ann Arbor, Michigan, April 1972, CONF-730414-P1, pp. 137-158, U.S. Atomic Energy Commission (1972).
  • H. U. WIDER, J. F. JACKSON, L. L. SMITH, and D. T. EGGEN, “An Improved Analysis of Fuel Motion During an Overpower Excursion,” Proc. ANS Conf. Fast Reactor Safety, Beverly Hills, California, April 1974, CONF-740401, pp. 1541-1555, U.S. Atomic Energy Commission (1974).
  • A. E. WRIGHT, “Transient Overpower Test H-4,” ANL/RAS 74-30, Argonne National Laboratory (Nov. 1974).
  • R. J. PAGE, A. B. ROTHMAN, K. J. SCHMIDT, C. L. FINK, R. W. MORNING, R. K. LO, P. H. FROEHLE, and E. W. JOHNSON, “TREAT TOP Test H-6-Preliminary Results,” Trans. Am. Nucl. Soc., 28, 481 (1978).
  • B. W. SPENCER, L. BOVA, G. T. GOLDFUSS, D. RAGIDON, R. E. HENRY, and D. R. ARMSTRONG, “CAMEL Single Pin Fuel Sweepout Test C2,” Trans. Am. Nucl. Soc., 27, 503 (1977).
  • K. W. WONG, V. K. DHIR, and W. E. KASTENBERG, “A Study of Fuel Freezing and Channel Plugging During Hypothetical Overpower Transients,” Proc. Int. Mtg. Fast Reactor Safety and Related Physics, Chicago, October 1976, CONF-7610001, U.S. Energy Research and Development Administration (1976).
  • K. W. WONG, V. K.DHIR, and W. E. KASTENBERG, “A Mechanistic Study of Fuel Freezing, Channel Plugging, and Continued Coolability During Fast Reactor Overpower Excursions,” Nucl. Technol., 39, 121 (1978).
  • D. VARELA, W. E. KASTENBERG, and V. K. DHIR, “Implications of In-Channel Plugging During Fast Reactor Overpower Excursions,” submitted to Nucl. Technol.
  • “Preliminary Safety Analysis Report,” Clinch River Breeder Reactor, Project Management Corporation (1975).
  • “Final Safety Analysis Report,” Fast Flux Test Facility, Vol. 7, Appendix C (Dec. 1975).
  • W. W. MARR and R. M. CRAWFORD, “Porous Heat Generating Blockage in a Fuel Assembly,” Trans. Am. Nucl. Soc., 15, 350 (1972).

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