scholarly journals Spent fuel data base: commercial light water reactors. [PWR; BWR]

1979 ◽  
Author(s):  
M.J. Hauf ◽  
B.G. Kniazewycz
Keyword(s):  
Data Base ◽  
Light Water Reactors ◽  
Spent Fuel ◽  
Light Water ◽  
Water Reactors

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.

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.

Radial Power Profile of MOX and LEU Fuel Pellet Versus Burnup

2002 ◽  
Author(s):  
Gray S. Chang ◽  
Robert C. Pedersen
Keyword(s):  
Performance Evaluation ◽  
Fuel Pellet ◽  
Light Water Reactors ◽  
Spent Fuel ◽  
Light Water ◽  
Fuel Pellets ◽  
Mox Fuel ◽  
Power Profile ◽  
Fission Power ◽  
Water Reactors

One of challenge to burn the WG-Pu in Mixed Oxide (MOX) fuel in light water reactors (LWR) is to demonstrate that the differences between WG-MOX, RG-MOX, and LWR LEU fuel are minimal, and therefore, the commercial MOX and LEU fuel experience base is applicable. The MCWO-calculated Radial Power Profile of LEU, Weapons Grade-MOX and Reactor Grade-MOX fuel pellets at various burnups are similar toward the end of life (50 GWd/t). Therefore, the LEU fuel performance evaluation code — FRAPCON-3 with modifications, such as, the detailed fission power profiles versus burnup, can be used in the MOX fuel pellet performance analysis. MCWO also calculated the 240Pu/Pu ratio in WG-MOX versus burnup, which reaches an average of 31.25% at discharged burnup of 50 GWd/t. It meets the spent fuel standard for WG-Pu disposition in LWR.

Estimation of Spent Fuel Compositions from Light Water Reactors

2000 ◽  
Vol 37 (10) ◽  
pp. 924-933 ◽  
Author(s):  
Yoshihira ANDO ◽  
Kenji NISHIHARA ◽  
Hideki TAKANO
Keyword(s):  
Light Water Reactors ◽  
Spent Fuel ◽  
Light Water ◽  
Water Reactors

A new approach to spent nuclear fuel recycling for light water reactors in the frame of remix concept

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Light Water Reactors ◽  
New Approach ◽  
Light Water ◽  
Water Reactors
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