The release fractions of the five elements in the {epsilon}-phase ({sup 99}Tc, {sup 97}Mo, Ru, Rh, and Pd) as well as that of {sup 238}U are reported for the reaction of two oxide fuels (ATM-103 and ATM-106) in unsaturated tests under oxidizing conditions. The {sup 99}Tc release fractions provide a lower limit for the magnitude of the spent fuel reaction. The {sup 99}Tc release fractions indicate that a surface reaction might be the rate controlling mechanism for fuel reaction under unsaturated conditions and the oxidant is possibly H{sub 2}O{sub 2}, a product of alpha radiolysis of water
Ageing processes occurring during storage of spent nuclear fuel rods are safety-relevant both for st...
In order to assess the impact of α-radiolysis of water on the oxidative dissolution of spent fuel, a...
Tests designed to be similar to the unsaturated and oxidizing conditions expected in the candidate r...
The release of {sup 99}Tc can be used as a reliable marker for the extent of spent oxide fuel reacti...
The five-metal epsilon particle represents an important component with respect to the corrosion of s...
Assessing the performance of spent (used) nuclear fuel in geological repository requires quantificat...
International audienceFor underwater interim storage of spent UOX fuel assemblies it is necessary to...
In most deep disposal concepts, large amounts of hydrogen are expected to be produced by the anoxic ...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
Oxidation tests in dry air were conducted on four LWR spent fuels at 175{degrees} and 195{degrees}C ...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
Assessing the performance of Spent (or Used) Nuclear Fuel (UNF) in geological repository requires qu...
Two BWR fuels [64 and 71 (MWd)/kgU], one of which contained 2% Gd, and two PWR fuels [30 and 45 (MWd...
The purpose of this analysis/model report (AMR) is to assess the potential for uranium (U) (VI) comp...
The source term for the release of radionuclides from a nuclear waste repository is the waste form. ...
Ageing processes occurring during storage of spent nuclear fuel rods are safety-relevant both for st...
In order to assess the impact of α-radiolysis of water on the oxidative dissolution of spent fuel, a...
Tests designed to be similar to the unsaturated and oxidizing conditions expected in the candidate r...
The release of {sup 99}Tc can be used as a reliable marker for the extent of spent oxide fuel reacti...
The five-metal epsilon particle represents an important component with respect to the corrosion of s...
Assessing the performance of spent (used) nuclear fuel in geological repository requires quantificat...
International audienceFor underwater interim storage of spent UOX fuel assemblies it is necessary to...
In most deep disposal concepts, large amounts of hydrogen are expected to be produced by the anoxic ...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
Oxidation tests in dry air were conducted on four LWR spent fuels at 175{degrees} and 195{degrees}C ...
The behaviour and release of fission products during high-temperature annealing of irradiated UO2 sa...
Assessing the performance of Spent (or Used) Nuclear Fuel (UNF) in geological repository requires qu...
Two BWR fuels [64 and 71 (MWd)/kgU], one of which contained 2% Gd, and two PWR fuels [30 and 45 (MWd...
The purpose of this analysis/model report (AMR) is to assess the potential for uranium (U) (VI) comp...
The source term for the release of radionuclides from a nuclear waste repository is the waste form. ...
Ageing processes occurring during storage of spent nuclear fuel rods are safety-relevant both for st...
In order to assess the impact of α-radiolysis of water on the oxidative dissolution of spent fuel, a...
Tests designed to be similar to the unsaturated and oxidizing conditions expected in the candidate r...