Nuclear Engineering and Design

We propose a method for the in situ determination and discrimination of surface and volume activity in metallic or mixed (metallic/concrete) radioactive waste. Owing to its ability to evaluate the specific activities of radionuclides, such as 60 Co and 137 Cs, this method is particularly suitable for characterizing radioactive waste produced by the decommissioning of reactors and surrounding stru…

Environmental ScienceGlobal and Planetary ChangePhysical SciencesRadioactive contamination and transfer

This study evaluates the feasibility and performance of uranium-zirconium hydride (U-ZrH x ) fuel in a graphite-free AGR-like Fluoride Salt-Cooled High-Temperature Reactor (AGR-like FHR). This reactor concept combines the pin-type geometry of Advanced Gas-cooled Reactors (AGR) with the low-pressure, high-efficiency characteristics of molten salt coolants and Hastelloy-N as cladding, aiming to imp…

Materials ChemistryMaterials ScienceNuclear Materials and PropertiesPhysical Sciences
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