Physicochemical State of the Spent Fuel Leaving the Reactors

2001 ◽  
Author(s):  
Philippe Dehaudt
Keyword(s):  
Scientific Literature ◽  
Current Knowledge ◽  
Pressurized Water Reactors ◽  
Light Water Reactors ◽  
Spent Fuel ◽  
Pressurized Water ◽  
Light Water ◽  
Physicochemical State ◽  
Water Reactors ◽  
Irradiated Fuel

Abstract This review focuses on the current knowledge, updated at the end of 1999, about the physicochemical state of the fuels leaving light water reactors, and particularly pressurized water reactors in France. Accessible data in the scientific literature, or those acquired at the CEA, are particularly numerous. Their analysis and their synthesis are joined together to constitute a collection of references intended to the specialists in nuclear fuel and for all those which contribute to the studies on the storage or final disposal of the irradiated fuel.

Transmission Electron Microsopy of oxidized UO2 spent fuel

1986 ◽  
Vol 44 ◽  
pp. 478-479
Author(s):  
L. E. Thomas ◽  
J. M. McCarthy ◽  
E. R. Gilbert
Keyword(s):  
Electron Microscopy ◽  
Oxidation Behavior ◽  
Light Water Reactors ◽  
Spent Fuel ◽  
Air Oxidation ◽  
Light Water ◽  
Transmission Electron ◽  
Water Reactors ◽  
Oxidation Weight Gain ◽  
Insight Into

The possibility that spent fuel from commercial light-water reactors (LWRs) may be stored for extended periods before reprocessing or permanant disposal has led to interest to its oxidation behavior in air. Oxidation weight gain tests at 150 to 250°C indicate that spent LWR fuel oxidizes 10 to 100 times more rapidly than unirradiated UO2, but is much slower to break up into U3O8 powder. To gain insight into the mechanisms that control oxidation in spent fuel, pre- and post oxidation samples were examined by transmission electron microscopy.

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