Luis H Ortega
Luis H Ortega
Texas A&M University, Argonne National Laboratory
Verified email at tamu.edu
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
412016
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
292015
Sensitivity study for accident tolerant fuels: Property comparisons and behavior simulations in a simplified PWR to enable ATF development and design
KY Spencer, L Sudderth, RA Brito, JA Evans, CS Hart, A Hu, A Jati, ...
Nuclear Engineering and Design 309, 197-212, 2016
172016
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 (2-4), 70-76, 2017
152017
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
142010
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
122016
Sintered bentonite ceramics for the immobilization of cesium-and strontium-bearing radioactive waste
LH Ortega
Texas A & M University, 2010
32010
Development of a high density uranium nitride-uranium silicide composite accident tolerant fuel
LH Ortega, J Evans, SM McDeavitt
Transactions 110 (1), 999-1000, 2014
22014
Precursors for the immobilization of radioactive Cesium and Strontium from spent nuclear fuel
LH Ortega, SM McDeavitt
Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and …, 2007
12007
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
2020
Ion-Exchange Kinetics of Alpha-Zirconium Phosphate Nanoplatelets for Application in Targeted Alpha Therapy
JD Einkauf, SM McDeavitt, JD Burns
Journal Solvent Extraction and Ion Exchange 38 (6), 612-628, 2020
2020
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
2019
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
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
2013
Immobilization of Liquid Nitrate Waste Containing Cesium and Strontium in Sintered Bentonite Ceramics
LH Ortega, SM McDeavitt, MD Kaminski
2009
Sorption of Radionuclides to Building Materials and its Removal Using Simple Salts–15452
M Kaminski, C Mertz, L Ortega, N Kivenas
Magnesium 3, 10, 0
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
PLUTONIUM ELUTION FROM DGA RESIN WITH AHA OBSERVED IN SITU VIA XANES AND XAFS
LH Ortega, M Kaminski, J Kropf, C Mertz
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Articles 1–18