Cr-doped U3Si2 composite fuels under steam corrosion

High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y

(2020) E. Sooby Wood et al.   JOURNAL OF NUCLEAR MATERIALS

Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties

(2020) Bowen Gong et al.   JOURNAL OF ALLOYS AND COMPOUNDS

U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels

(2020) Bowen Gong et al.   JOURNAL OF NUCLEAR MATERIALS

Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry

(2019) Bowen Gong et al.   JOURNAL OF NUCLEAR MATERIALS

U 3 Si 2 behavior in H 2 O: Part I, flowing steam and the effect of hydrogen

(2018) E. Sooby Wood et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal and transport properties of U 3 Si 2

(2018) Daniel J. Antonio et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal and mechanical properties of polycrystalline U3Si2 synthesized by spark plasma sintering

(2018) Afiqa Mohamad et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Consolidation of commercial-size UO2 fuel pellets using spark plasma sintering and microstructure/microchemical analysis

(2018) Bowen Gong et al.   MRS Communications

Grain size and phase purity characterization of U3Si2 fuel pellets

(2018) Rita E. Hoggan et al.   JOURNAL OF NUCLEAR MATERIALS

Spark plasma sintering and microstructural analysis of pure and Mo doped U 3 Si 2 pellets

(2017) Denise Adorno Lopes et al.   JOURNAL OF NUCLEAR MATERIALS

The effect of aluminum additions on the oxidation resistance of U 3 Si 2

(2017) E. Sooby Wood et al.   JOURNAL OF NUCLEAR MATERIALS

Dense nanocrystalline UO2+x fuel pellets synthesized by high pressure spark plasma sintering

(2017) Tiankai Yao et al.   JOURNAL OF THE AMERICAN CERAMIC SOCIETY

Determination of mechanical behavior of U 3 Si 2 nuclear fuel by microindentation method

(2017) Kathryn E. Metzger et al.   PROGRESS IN NUCLEAR ENERGY

Fabrication and microstructural analysis of UN-U 3 Si 2 composites for accident tolerant fuel applications

(2016) Kyle D. Johnson et al.   JOURNAL OF NUCLEAR MATERIALS

Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U 3 Si 2 ) with increased uranium loading

(2016) Luis H. Ortega et al.   JOURNAL OF NUCLEAR MATERIALS

Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation

(2015) Jason M. Harp et al.   JOURNAL OF NUCLEAR MATERIALS

UO 2 –UN composites with enhanced uranium density and thermal conductivity

(2015) Jae Ho Yang et al.   JOURNAL OF NUCLEAR MATERIALS

Thermophysical properties of U3Si2 to 1773 K

(2015) J.T. White et al.   JOURNAL OF NUCLEAR MATERIALS

Comparison of the accident process, radioactivity release and ground contamination between Chernobyl and Fukushima-1

(2015) Tetsuji Imanaka et al.   JOURNAL OF RADIATION RESEARCH

Examining the Nuclear Accident at Fukushima Daiichi

(2012) E. D. Blandford et al.   Elements

Improving fracture toughness and hardness of Fe2B in high boron white cast iron by chromium addition

(2010) Zhifu Huang et al.   MATERIALS & DESIGN