Lv2
194 积分 2022-07-15 加入
Effect of post-weld heat treatment on a friction stir welded joint between 9Cr-ODS and CLF-1 steels
3个月前
已完结
Research on the physical properties of a novel high-temperature, high-efficiency shielding composite material for nuclear reactors
3个月前
已完结
A high temperature W2B–W composite for fusion reactor shielding
4个月前
已完结
Tungsten Carbide compact primary shielding for Small Medium Reactor
4个月前
已完结
Design of cemented tungsten carbide and boride-containing shields for a fusion power plant
4个月前
已完结
Applicability of Hydride Materials for Radiation Shielding in Helical Reactor FFHR-d1
4个月前
已完结
Thermal mechanical evaluation of candidate tokamak divertor elements informing fusion materials design windows
4个月前
已完结
Tungsten boride shields in a spherical tokamak fusion power plant
4个月前
已完结
Mechanical characterisation of tungsten–1 wt.% yttrium oxide as a function of temperature and atmosphere
4个月前
已完结
The influence of W2B5 addition on microstructure and thermoelectric properties of B4C ceramic
4个月前
已完结
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