Development of the Process for the Recovery and Conversion of233UF6Chemisorbed in NaF Traps from the Molten Salt Reactor Remediation Project

Author:

Cul Guillermo D. Del1,Icenhour Alan S.1,Simmons Darrell W.1

Affiliation:

1. Oak Ridge National Laboratory 1 Bethel Valley Road, Oak Ridge, Tennessee 37831-6181

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference18 articles.

1. Experience with the Molten-Salt Reactor Experiment

2. E. L. COMPERE, S. S. KIRSLIS, E. G. BOHLMANN, F. R. BLANKENSHIP, and W. R. GRIMES, “Fission Product Behavior in the Molten Salt Reactor Experiment,” ORNL-4865, Oak Ridge National Laboratory (1975).

3. Fluorine generation by gamma radiolysis of a fluoride salt mixture

4. H. C. SAVAGE, E. L. COMPERE, and J. M. BAKER, “Gamma Irradiation of a Simulated MSRE Fuel Salt in the Solid Phase,” Reactor Chemistry Division Annual Progress Report, ORNL-3591, Oak Ridge National Laboratory (1964).

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