Behavior of uranium and zirconium in direct transport tests with irradiated EBR-II fuel

Citation
R. Ahluwalia et al., Behavior of uranium and zirconium in direct transport tests with irradiated EBR-II fuel, NUCL TECH, 126(3), 1999, pp. 289-302
Citations number
11
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR TECHNOLOGY
ISSN journal
00295450 → ACNP
Volume
126
Issue
3
Year of publication
1999
Pages
289 - 302
Database
ISI
SICI code
0029-5450(199906)126:3<289:BOUAZI>2.0.ZU;2-Q
Abstract
A theoretical model is used to analyze the transport of U and Zr in electro refining of irradiated binary Experimental Breeder Reactor-II fuel, A limit ing-current hypothesis is advanced to explain the observed dissolution of Z r in the presence of U at high, intermediate, and low cell voltages. The in ternal diffusion model predicts the existence of a critical current and a c ritical voltage for Zr oxidation. Experimental results are presented for a test designed and run based on optimum conditions determined from the model to dissolve U expediently while retaining Zr in the anode baskets. A simpl e model of kinetic exchange reactions between salt-phase U and Cd-phase Zr is formulated to explain the measured electrodeposition of Zr on the solid cathode. It is shown that the Zr content of the deposit is overpredicted if the pool is considered isolated and grossly underpredicted if the salt pha se is equilibrated instantaneously with the Cd pool. Finally, the aspects o f anodic current efficiency and cathodic collection efficiency are discusse d taking into account shorting between the dissolution baskets and the Cd p ool, multiple oxidation stares of Zr, and the exchange reactions between th e fuel and UCl3 prior to electrotransport.