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46 积分 2024-09-11 加入
Deployment study of accident tolerant fuels in small modular advanced high temperature reactor
27天前
已完结
Neutronic performance of uranium nitride composite fuels in a PWR
27天前
已完结
Chemical interaction and compatibility of uranium mononitride and alumina forming austenitic stainless steel
27天前
已完结
Uranium–zirconium hydride fuel properties
27天前
已完结
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)
27天前
已完结
UN and U3Si2 composites densified by spark plasma sintering for accident-tolerant fuels
27天前
已完结
Thermal Conductivity of UO2–BeO–Gd2O3 Nuclear Fuel Pellets
27天前
已完结
Theoretical study on the mechanical and thermal properties of uranium dioxide doped with lanthanide fission products
27天前
已完结
Swelling due to the partition of soluble fission products between the grey phase and uranium dioxide
27天前
已完结
Diffusion of solid fission products in UO2 and UO2+x
27天前
已完结
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