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Investigation of Polonium Removal Systems for Lead-Bismuth Cooled Fast Reactors Using a Tellurium Surrogate: Part II

[+] Author Affiliations
Eric Loewen

Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID

Shuji Ohno

Japan Nuclear Cycle Development Institute, O-arai-machi, Ibaraki-ken, Japan

Paper No. ICONE12-49396, pp. 77-82; 6 pages
  • 12th International Conference on Nuclear Engineering
  • 12th International Conference on Nuclear Engineering, Volume 1
  • Arlington, Virginia, USA, April 25–29, 2004
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4687-3 | eISBN: 0-7918-3735-1
  • Copyright © 2004 by JSME


The alkaline extraction method is being investigated as a method to remove polonium from a lead-bismuth cooled reactor. Tellurium was used as a surrogate for polonium for these experiments to quantify the migration from lead-bismuth to molten alkaline (NaOH). Experiments provided direct evidence that molten NaOH can effectively remove tellurium from lead-bismuth. A reduction of three to four orders of magnitude in the tellurium concentration in the metals was measured in the experiments. The experimental results also showed a higher than expected concentration of NaOH in the lead or lead-bismuth. A comparison between experiments operated at 427°C and 500°C respectively indicates that the higher operating temperature produces a higher removal rate of Te. Experiments where hot NaOH was injected into the crucible at the same temperature as the lead-bismuth eutectic (LBE) resulted in the rapid removal rate of Te and remained constant until the experiment was completed. This paper is a continuation of the results reported in the previous ICONE paper, (ICONE11-36614) providing an experimental update.

Copyright © 2004 by JSME



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