Lv1
46 积分 2024-09-11 加入
Deployment study of accident tolerant fuels in small modular advanced high temperature reactor
12天前
已完结
Neutronic performance of uranium nitride composite fuels in a PWR
12天前
已完结
Chemical interaction and compatibility of uranium mononitride and alumina forming austenitic stainless steel
12天前
已完结
Uranium–zirconium hydride fuel properties
12天前
已完结
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)
12天前
已完结
UN and U3Si2 composites densified by spark plasma sintering for accident-tolerant fuels
12天前
已完结
Thermal Conductivity of UO2–BeO–Gd2O3 Nuclear Fuel Pellets
12天前
已完结
Theoretical study on the mechanical and thermal properties of uranium dioxide doped with lanthanide fission products
12天前
已完结
Swelling due to the partition of soluble fission products between the grey phase and uranium dioxide
12天前
已完结
Diffusion of solid fission products in UO2 and UO2+x
12天前
已完结
皖公网安备34019202002308
