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Luis H Ortega
Luis H Ortega
Texas A&M University, Argonne National Laboratory
Verified email at tamu.edu - Homepage
Title
Cited by
Cited by
Year
Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3 Si2) with increased uranium loading
LH Ortega, BJ Blamer, JA Evans, SM McDeavitt
Journal of Nuclear Materials 471, 116-121, 2016
852016
Synthesis of high capacity cathodes for lithium-ion batteries by morphology-tailored hydroxide co-precipitation
D Wang, I Belharouak, LH Ortega, X Zhang, R Xu, D Zhou, G Zhou, ...
Journal of Power Sources 274, 451-457, 2015
762015
Manufacture of a UO2-Based Nuclear Fuel with Improved Thermal Conductivity with the Addition of BeO
CB Garcia, RA Brito, LH Ortega, JP Malone, SM McDeavitt
Metallurgical and Materials Transactions E 4 (2), 70-76, 2017
272017
Pollucite and feldspar formation in sintered bentonite for nuclear waste immobilization
LH Ortega, MD Kaminski, SM McDeavitt
Applied clay science 50 (4), 594-599, 2010
242010
Sorption of radionuclides to building materials and its removal using simple wash solutions
M Kaminski, C Mertz, L Ortega, N Kivenas
Journal of Environmental Chemical Engineering 4 (2), 1514-1522, 2016
232016
Thermal conductivity of uranium metal and uranium-zirconium alloys fabricated via powder metallurgy
LH Ortega, B Blamer, KM Stern, J Vollmer, SM McDeavitt
Journal of Nuclear Materials 531, 151982, 2020
102020
Separate-effects validation experiments for models of fracture in ceramic nuclear fuel
BW Spencer, NE Woolstenhulme, LA Emerson, J Yeh, DD Imholte, ...
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019
82019
Experimentally Validated Multiphysics Modeling of Fracture Induced by Thermal Shocks in Sintered UO2 Pellets
LD McClenny, MI Butt, MG Abdoelatef, MJ Pate, KL Yee, H Rajendran, ...
https://www.sciencedirect.com/science/article/pii/S0022311522002094, 2022
62022
Thermal-shock experiments for separate-effects validation of UO2 fuel fracture models
LH Ortega, KL Yee, D Perez-Nunez, SM McDeavitt, C Steinman, ...
Journal of Nuclear Materials 572, 154035, 2022
42022
Sintered bentonite ceramics for the immobilization of cesium-and strontium-bearing radioactive waste
LH Ortega
Texas A & M University, 2010
42010
Improved leach resistance of FLiBe by conversion to a substituted fluorapatite
LH Ortega, RJ Livingston, SM McDeavitt
Nuclear Materials and Energy, 2022
22022
Ion-Exchange Kinetics of Alpha-Zirconium Phosphate Nanoplatelets for Application in Targeted Alpha Therapy
JD Einkauf, LH Ortega, SM McDeavitt, JD Burns
Journal Solvent Extraction and Ion Exchange 38 (6), 612-628, 2020
22020
Development of a high density uranium nitride-uranium silicide composite accident tolerant fuel
LH Ortega, J Evans, SM McDeavitt
ANS 2014, 2014
22014
Cermet waste forms for waste streams from advanced aqueous processing of spent nuclear fuels-11348
L Ortega, Z Zeng, M Kaminski, J Cunnane, K Natesan
Proceedings of Waste Management, 2011
22011
Concept Descriptions for the VTR Rabbit System and Driver Fuel Test Assemblies
SM McDeavitt, D Wootan, M Kimber, KV Kirkland, LH Ortega, ...
Nuclear Science and Engineering 197 (11), 2840-2852, 2023
12023
Nuclear fuel cycle waste stream immobilization with cermets for improved thermal properties and waste consolidation
LH Ortega, MD Kaminski, Z Zeng, J Cunnane
Journal of nuclear materials 438 (1-3), 126-133, 2013
12013
Precursors for the immobilization of radioactive Cesium and Strontium from spent nuclear fuel
LH Ortega, SM McDeavitt
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2007
12007
An experimentally validated mesoscale model for the effective thermal conductivity of U-Zr fuels
F Badry, M Singh, LH Ortega, SM Mcdeavitt, K Ahmed
Journal of Nuclear Materials 574, 154203, 2023
2023
Design and Demonstration of a Rabbit Experiment System for the Versatile Test Reactor
AW Sean M. McDeavitt, Mark Kimber, Karen Kirkland, Luis H. Ortega, Delia ...
2020 ANS Virtual Winter Meeting: Nuclear is good for you, 2020
2020
Separate-Effects Validation Experiments for Models of Fracture in Ceramic Nuclear Fuel
H Spencer, Benjamin W, Woolstenhulme, Nicolas E, Emerson, Leigh A, Yeh ...
Conference: Top Fuel 2019, Seattle, WA,, 2019
2019
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