Jim Kiggans

Oak Ridge National Laboratory — United States

Materials Science · Physical Sciences

28h-index3.6kcitations134works0.02yr avg
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Research Topics

Advanced ceramic materials synthesis(47), Microwave-Assisted Synthesis and Applications(28), Nuclear Materials and Properties(25), Advancements in Battery Materials(21), Advanced materials and composites(18)

Publications134 total

Fabric properties and electric efficiency limits of mechanical moisture extraction from fabrics
Drying Technology·2021· 7 citedOpen Access
Effect of Composition on the Phase Structure and Magnetic Properties of Ball-Milled LaFe11.71-xMnxSi1.29H1.6 Magnetocaloric Powders
Magnetochemistry·2021· 3 citedOpen Access
Characterization of high thermal conductivity fuel surrogates before and after ion irradiation
Journal of Nuclear Materials·2021· 13 citedOpen Access
Processing of complex-shaped collimators made via binder jet additive manufacturing of B4C and pressureless melt infiltration of Al
Materials & Design·2019· 54 citedOpen Access
A 6 MW/m<sup>2</sup> High Heat Flux Testing Facility of Irradiated Materials Using Infrared Plasma-Arc Lamps
Fusion Science & Technology·2019· 6 citedOpen Access
Documentation Package Supporting Fabrication of Doped UO&lt;sub&gt;2&lt;/sub&gt; Samples for MiniFuel Irradiation and Fission Gas Release Benchmarking
2019Open Access
Fabrication of UO2-Mo composite fuel with enhanced thermal conductivity from sol-gel feedstock
Journal of Nuclear Materials·2019· 41 citedOpen Access
Fabrication and Irradiation Test Plan for Fully Ceramic Microencapsulated Fuels
2019Open Access
Synthesis and Characterization of UO&lt;sub&gt;2&lt;/sub&gt; Feedstocks containing Controlled Dopants
2019· 4 citedOpen Access
Fabrication of Fully Ceramic Microencapsulated Compacts for Miniature Fuel Specimen Irradiation
Transactions of the American Nuclear Society - Volume 121·2019
Fabrication and microstructural analysis of ceramic fuel derived from sol-gel and powder routes
2018· 2 citedOpen Access
Surface morphology of Tungsten-F82H after high-heat flux testing using plasma-arc lamps
Nuclear Materials and Energy·2018· 5 citedOpen Access
Production of near‐full density uranium nitride microspheres with a hot isostatic press
Journal of the American Ceramic Society·2018· 16 citedOpen Access
Examination of HIP for production of high density UN kernels
2017· 6 citedOpen Access
Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature
Journal of Nuclear Materials·2017· 41 citedOpen Access
UN TRISO Compaction in SiC for FCM Fuel Irradiations
2016· 3 citedOpen Access
Hydrothermal corrosion of silicon carbide joints without radiation
Journal of Nuclear Materials·2016· 19 citedOpen Access
M3FT-16OR020202112 - Report on viability of hydrothermal corrosion resistant SiC/SiC Joint development
2016· 4 citedOpen Access
Production of LEU Fully Ceramic Microencapsulated Fuel for Irradiation Testing
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)·2016· 5 cited
Experimental Study of the Maximum Resolution and Packing Density Achievable in Sintered and Non-Sintered Binder-Jet 3D Printed Steel Microchannels
Volume 2A: Advanced Manufacturing·2015· 16 cited
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Frequent Co-authors

H. D. Kimrey(7), T. N. Tiegs(7), Kurt A. Terrani(6), Nancy J. Dudney(5), Costas Tsouris(5), Richard T. Mayes(5), David W. DePaoli(5), Sheng Dai(5), Yutai Katoh(5), W K Yang(5), Yukinori Yamamoto(5), William H. Peter(5), Adrian S. Sabau(5), Stephen D. Nunn(5), Ketki Sharma(4), Sotira Yiacoumi(4), Beth L. Armstrong(4), Mark A. Janney(4), Jianlin Li(4), Claus Daniel(4)