Analysis of uranium in dissolver solution of fast reactor carbide fuel reprocessing

Analysis of uranium in dissolver solution of fast reactor carbide fuel reprocessing

Uranium in simulated dissolver solution of FBTR mixed carbide fuel containing fission products is analyzed by modified Davies–Gray method. The uranium is analyzed after the sample is evaporated with 1 M H 2 SO 4 and followed all the steps carried out by Davies–Gray method. The proposed method assure...

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Veröffentlicht in:Journal of radioanalytical and nuclear chemistry 2014-04, Vol.300 (1), p.115-119
Hauptverfasser: Chinnusamy, A., Velavendan, P., Ganesh, S., Pandey, N. K., Mudali, U. K., Natarajan, R.
Format: Artikel
Sprache:eng
Schlagworte:
Chemistry
Chemistry and Materials Science
Diagnostic Radiology
Dissolvers
Evaporation
Fission products
Hadrons
Heavy Ions
Inorganic Chemistry
Nuclear Chemistry
Nuclear engineering
Nuclear fuel cycle
Nuclear fuels
Nuclear Physics
Nuclear reactors
Physical Chemistry
Reprocessing
Uranium
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Zusammenfassung:Uranium in simulated dissolver solution of FBTR mixed carbide fuel containing fission products is analyzed by modified Davies–Gray method. The uranium is analyzed after the sample is evaporated with 1 M H 2 SO 4 and followed all the steps carried out by Davies–Gray method. The proposed method assures analysis of uranium in dissolver solution of FBTR fuel can be titrated directly without prior separation of fission products.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-014-2951-2