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Technical Paper

A Radionuclide Trap for Liquid-Metal-Cooled Reactors

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Pages 101-109 | Published online: 10 May 2017

References

  • W. L. KUHN, “Activated Corrosion Product Radiation Levels in the FFTF Heat Transport System Cells and Closed Loop System Modules,” HEDL-TME 76-10, Hanford Engineering Development Laboratory (Sep. 1977).
  • “Sodium Engineering and Technology Technical Progress Report: January, February and March 1977,” HEDL-TME 77-36, Hanford Engineering Development Laboratory (1977).
  • D. L. SMITH and R. H. LEE, “Characterization of the Vanadium Wire Equilibration Method for Measurement of Oxygen Activity in Liquid Sodium,” ANL-7891, Argonne National Laboratory (Jan. 1972).
  • W. F. BREHM, “Effect of Oxygen in Sodium Upon Radionuclide Release from Austenitic Stainless Steel,” IAEA Specialists’ Conf. Fission and Corrosion Product Behavior, Dimitrovgrad, USSR, September 8–11, 1975, HEDL-SA-985, Hanford Engineering Development Laboratory.
  • R. R. MATHEWS, “Location and Repair of a Leak in the Dounreay Fast Reactor Primary Circuit,” J. Br. Nucl. Soc., 8, 168 (July 1969).

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