Interim-storage examination of irradiated pickering-a and bruce-a fuel bundles following up to approximately 140 months of storage in dry air at 150 degrees c
Interim-storage examination of irradiated pickering-a and bruce-a fuel bundles following up to 93 months of storage in moisture-saturated air at 150 degrees c
Gamma radiolysis effects on leaching behavior of ceramic materials for nuclear fuel waste immobilization containers
Application of electrochemical methods in the development of models for fuel dissolution and container corrosion under nuclear waste disposal conditions
The electrochemistry of hydrogen peroxide on uo2 electrodes and the influence of hydrogen peroxide on the corrosion of uo2
Xps procedure : determination of concentrations from xps data using empirical atomic sensitivity factors