Similar Items: Validation of the oxidative dissolution model for used CANDU fuel.
- An electrochemistry-based model for the dissolution of UO2.
- Validation of the ORIGENS code for predicting radionuclide inventories in used CANDU fuel.
- Chemical Dissolution of Metal Oxides.
- Factors affecting the differences in reactivity and dissolution rates between UO2 and spent nuclear fuel.
- Dissolution models for glassy waste forms.
- A copper container corrosion model for the inroom emplacement of used CANDU fuel.
Author: Shoesmith, D. W.
- The cathodic reduction of dioxygen on uranium oxide in dilute alkaline aqueous solution.
- An electrochemistry-based model for the dissolution of UO2.
- Crevice corrosion and the lifetime performance of titanium nuclear waste containers.
- The resistance of titanium to pitting, microbially induced corrosion and corrosion in unsaturated conditions.
- Industrial experience with titanium.
- Hydrogen absorption and lifetime performance of titanium nuclear waste containers.
Author: Sunder, S.
- Alpha, beta and gamma dose rates in water in contact with used Candu UO2 fuel.
- Corrosion of UN in water.
- Prediction of longterm behaviour for nuclear waste disposal.
- Factors affecting the differences in reactivity and dissolution rates between UO2 and spent nuclear fuel.
- XPS, XRD and SEM study of oxidation of UO2 by air in gamma radiation at 150°C.
- An electrochemistry-based model for the dissolution of UO2.