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72 积分 2026-03-02 加入
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)
3天前
已完结
Surface adsorption and dissolution mechanisms of UO2 (110) and (111) in oxidizing environments: Insights for sustainable nuclear fuel recycling
7天前
已完结
Corrosion behavior of high uranium density fuels
10天前
已完结
Steam oxidation of uranium mononitride in pure and reducing steam atmospheres to 1200 °C
11天前
已完结
Thermal expansion and steam oxidation of uranium mononitride analysed via in situ neutron diffraction
11天前
已完结
Thermal expansion and degradation of uranium mononitride under high-temperature oxidative conditions
11天前
已完结
Uranium nitride (UN) pellets with controllable microstructure and phase – fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties
11天前
已完结
The true thermal expansion of uranium mononitride
11天前
已关闭
Functional Groups‐Regulated Organic Semiconductors for Efficient Artificial Photosynthesis of Hydrogen Peroxide
12天前
已完结
Improved corrosion resistance and its origins in nitrided U-2.0Nb alloy assisted by pulsed laser
13天前
已完结
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