The influence of high burn-up structured material on UO2 corrosion has been studied in an autoclave experiment. The experiment was conducted on spent fuel fragments with an average burn-up of 67 GWd/tHM. They were corroded in a simplified groundwater containing 33 mM dissolved H-2 for 502 days. All redox sensitive elements were reduced. The reduction continued until a steady-state concentration was reached in the leachate for U at 1.5 x 10(-10) M and for Pu at 7 x 10(-11) M. The instant release of Cs during the first 7 days was determined to 3.4% of the total inventory. However, the Cs release stopped after release of 3.5%. It was shown that the high burn-up structure did not enhance fuel corrosion. (C) 2009 Elsevier B.V. All rights reserve...
In order to elucidate fuel wash-out behavior after the degraded secondary failure of LWR fuel rods, ...
Release of long-lived radionuclides such as plutonium and caesium from spent nuclear fuel in deep ge...
Data on the effects of nuclear fuel burnup on dissolution rates and U losses of a few fuel types are...
The influence of high burn-up structured material on UO2 corrosion has been studied in an autoclave ...
A fission product and Pu rich porous structure forms at the radial periphery of LWR fuel pellet at a...
Corrosion of spent UO{sub 2} fuel has been studied in experiments conducted for nearly six years. Ox...
The corrosion behaviour of irradiated MOX fuel (47 GWd/tHM) has been studied in an autoclave experim...
In case of a canister failure in a deep bedrock repository for nuclear fuel, the release of radiotox...
The corrosion behaviour of irradiated MOX fuel (47 GWd/tHM) has been studied in an autoclave experim...
Although the general environment of the proposed repository at Yucca Mountain is expected to be oxid...
In most deep disposal concepts, large amounts of hydrogen are expected to be produced by the anoxic ...
The safety assessment of spent nuclear fuel under permanent disposal conditions requires examination...
The leaching of a high-burn-up spent nuclear fuel (48 MWd/KgU) has been studied in a carbonate-conta...
International audienceFor underwater interim storage of spent UOX fuel assemblies it is necessary to...
To assess the long-term leaching behaviour of UO2, the main constituent of spent nuclear fuel, the o...
In order to elucidate fuel wash-out behavior after the degraded secondary failure of LWR fuel rods, ...
Release of long-lived radionuclides such as plutonium and caesium from spent nuclear fuel in deep ge...
Data on the effects of nuclear fuel burnup on dissolution rates and U losses of a few fuel types are...
The influence of high burn-up structured material on UO2 corrosion has been studied in an autoclave ...
A fission product and Pu rich porous structure forms at the radial periphery of LWR fuel pellet at a...
Corrosion of spent UO{sub 2} fuel has been studied in experiments conducted for nearly six years. Ox...
The corrosion behaviour of irradiated MOX fuel (47 GWd/tHM) has been studied in an autoclave experim...
In case of a canister failure in a deep bedrock repository for nuclear fuel, the release of radiotox...
The corrosion behaviour of irradiated MOX fuel (47 GWd/tHM) has been studied in an autoclave experim...
Although the general environment of the proposed repository at Yucca Mountain is expected to be oxid...
In most deep disposal concepts, large amounts of hydrogen are expected to be produced by the anoxic ...
The safety assessment of spent nuclear fuel under permanent disposal conditions requires examination...
The leaching of a high-burn-up spent nuclear fuel (48 MWd/KgU) has been studied in a carbonate-conta...
International audienceFor underwater interim storage of spent UOX fuel assemblies it is necessary to...
To assess the long-term leaching behaviour of UO2, the main constituent of spent nuclear fuel, the o...
In order to elucidate fuel wash-out behavior after the degraded secondary failure of LWR fuel rods, ...
Release of long-lived radionuclides such as plutonium and caesium from spent nuclear fuel in deep ge...
Data on the effects of nuclear fuel burnup on dissolution rates and U losses of a few fuel types are...