DFT and experimental study on the thermal conductivity of U3O8 and U3O8-X;(X= Al and Mo)

JI Ranasinghe, L Malakkal, B Szpunar, A Prasad… - Journal of Nuclear …, 2021 - Elsevier
In this article, a theoretical and experimental investigation on the phonon thermal
conductivity (κ L) of α-U 3 O 8 in the temperature range of 300 to 1000 K is reported. The …

[图书][B] Polymer derived ceramics: Processing-structure-property relationships

SC Zunjarrao - 2008 - search.proquest.com
Silicon carbide (SiC) is an important ceramic, most commonly used because of its excellent
properties such as high strength, high modulus, excellent creep resistance and its high …

[PDF][PDF] COMPREHENSIVE INVESTIGATION OF SELECTED URANIUM COMPOUNDS WITH APPLICATION FOR CLEAN ENERGY

JI Ranasinghe - 2022 - harvest.usask.ca
The focus of this thesis mainly revolves investigation of the thermal properties of triuranium
octoxide (U3O8), uranium di-aluminide (UAl2), U3O8-Mo, and U3O8-Al nuclear fuels. They …

Structure-property relationships in polymer derived amorphous/nano-crystalline silicon carbide for nuclear applications

SC Zunjarrao, AK Singh… - International …, 2006 - asmedigitalcollection.asme.org
Silicon carbide (SiC) is a promising candidate for several applications in nuclear reactors
owing to its high thermal conductivity, high melting temperature, good chemical stability, and …

Advanced Process Model for Polymer Pyrolysis and Uranium Ceramic Material Processing

X Wang, SC Zunjarrao, H Zhang… - International …, 2006 - asmedigitalcollection.asme.org
Silicon carbide (SiC) based uranium ceramic material can be fabricated as hosts for ultra
high temperature applications, such as gas-cooled fast reactor fuels and in-core materials. A …

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

H Zhang, RP Singh - 2008 - osti.gov
Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the
development of new materials that can operate at the higher temperatures expected in these …

Development of a mesoscopic particle model for synthesis of uranium-ceramic nuclear fuel

X Wang, H Zhang, L Zheng, J Wei - International journal of heat and mass …, 2009 - Elsevier
A novel technique has been developed to fabricate uranium-ceramic nuclear fuel using the
depleted uranium (DU), U3O8 powder, and allylhydridopolycarbosilane (AHPCS) polymer …

Application of Meshless Pore-Level Model to Pyrolysis and Synthesis of Nuclear Fuels

X Wang, H Zhang, L Zheng - Heat Transfer …, 2007 - asmedigitalcollection.asme.org
Uranium-ceramic nuclear fuels can be fabricated through pyrolysis-based materials
processing technique. This technique requires lower energy compared to sintering route …