Nuclear Engineering and Design
Spatial gradients of corrosion deposits in steam generator tubes of the BN-800 sodium-cooled reactor
Preliminary experimental study of LBE evaporation behavior between 200–400 °C under argon atmosphere
Natural circulation in a Multi-Channel flow loop: effects of heating configuration and working fluid
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…
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…
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