Fluidized oxidative disaggregation of pelletized nuclear fuel

Autor:	N. A. Nilov, E. M. Valuev, E. I. Rybakov, A. T. Ageenkov, V. F. Savel'ev, E. N. Gal'perin
Rok vydání:	1973
Předmět:	Nuclear fuel Uranium dioxide Radiochemistry General Engineering Spent nuclear fuel Thorium fuel cycle chemistry.chemical_compound Nuclear reprocessing Uranium hexafluoride Nuclear Energy and Engineering chemistry Uranate MOX fuel Nuclear chemistry
Zdroj:	Soviet Atomic Energy. 35:1052-1054
ISSN:	1573-8205 0038-531X
DOI:	10.1007/bf01215833
Popis:	Pred i spe r sa l of nuclear fuel as a resul t of oxidation of uranium dioxide to uranyl uranate (mixed u r anous u r an i c oxide, U30 a) opens the way for more advantageous use of the advantages of fluidized-bed f luorinators [1-5]. This accounts for the search for an opt imum-design fluidized-bed reac tor and basic pa r ame te r s of a p rocess involving oxidative breakdown of pelletized nuclear fuel for power reac tor fuel elements. The charac ter i s t ics of the uranium dioxide employed in the work are listed in Table 1, The inert packing employed in the fluidized-bed fluorinator was aluminum oxide 100 # mesh and 500 t~ mesh.
Databáze:	OpenAIRE
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