The effects of hydrogen peroxide, H2O2, on UO2 corrosion is investigated in aerated deionized water in two types of situations. The H2O2 species is either added to water or produced by radiolysis at UO2/H2O interfaces. The concentrations vary in the range 10−5–10−1 mol l−1. The radiolysis is induced by irradiating the UO2/H2O interfaces with a He2+-beam emerging from the UO2 discs into the solutions. Both the evolution of the aqueous solutions and the UO2 surfaces are characterised. In both types of experiments, the alteration of UO2 results in the formation of the same secondary phase, an hydrated uranium peroxide called studtite (UO2(O)2 · 4H2O). However, the uranium release at the interface differs strikingly. It is much higher when H2O2...
In case of a canister failure in a deep bedrock repository for nuclear fuel, the release of radiotox...
In most deep disposal concepts, large amounts of hydrogen are expected to be produced by the anoxic ...
To assess the long-term leaching behaviour of UO2, the main constituent of spent nuclear fuel, the o...
The effects of hydrogen peroxide, H2O2, on UO2 corrosion is investigated in aerated deionized water ...
In this work, the oxidation of UO2 by the radiolysis products of water at the solid/solution interfa...
X-ray diffraction has been used to probe the radiolytic corrosion of uranium dioxide.Single crystal ...
Understanding the possible change in UO2 surface reactivity after exposure to oxidants is of key imp...
X-ray diffraction has been used to probe the radiolytic corrosion of uranium dioxide. Single crystal...
The radiolysis of water due to ionizing radiation results in the production of electrons, H· atoms, ...
Dissolution of the UO2 matrix is one of the potential routes for radionuclide release in a future de...
Release of long-lived radionuclides such as plutonium and caesium from spent nuclear fuel in deep ge...
Release of long-lived radionuclides such as plutonium and caesium from spent nuclear fuel in deep ge...
For the first time the effect of hydrogen peroxide on the dissolution of electrodeposited uranium ox...
Uranium mononitride, UN, is considered a potential accident tolerant fuel due to its high uranium d...
Spent nuclear fuel is composed of ≈95% UO2, and upon storage in geologic repository the fuel itse...
In case of a canister failure in a deep bedrock repository for nuclear fuel, the release of radiotox...
In most deep disposal concepts, large amounts of hydrogen are expected to be produced by the anoxic ...
To assess the long-term leaching behaviour of UO2, the main constituent of spent nuclear fuel, the o...
The effects of hydrogen peroxide, H2O2, on UO2 corrosion is investigated in aerated deionized water ...
In this work, the oxidation of UO2 by the radiolysis products of water at the solid/solution interfa...
X-ray diffraction has been used to probe the radiolytic corrosion of uranium dioxide.Single crystal ...
Understanding the possible change in UO2 surface reactivity after exposure to oxidants is of key imp...
X-ray diffraction has been used to probe the radiolytic corrosion of uranium dioxide. Single crystal...
The radiolysis of water due to ionizing radiation results in the production of electrons, H· atoms, ...
Dissolution of the UO2 matrix is one of the potential routes for radionuclide release in a future de...
Release of long-lived radionuclides such as plutonium and caesium from spent nuclear fuel in deep ge...
Release of long-lived radionuclides such as plutonium and caesium from spent nuclear fuel in deep ge...
For the first time the effect of hydrogen peroxide on the dissolution of electrodeposited uranium ox...
Uranium mononitride, UN, is considered a potential accident tolerant fuel due to its high uranium d...
Spent nuclear fuel is composed of ≈95% UO2, and upon storage in geologic repository the fuel itse...
In case of a canister failure in a deep bedrock repository for nuclear fuel, the release of radiotox...
In most deep disposal concepts, large amounts of hydrogen are expected to be produced by the anoxic ...
To assess the long-term leaching behaviour of UO2, the main constituent of spent nuclear fuel, the o...