Dr. Joshua T. White is a Senior Scientist at Materials and Science and Technology Division of Los Alamos National Laboratory. His research interests include high temperature materials synthesis and testing of novel nuclear fuel in accident scenarios as well as characterizing the thermophysical properties. He currently leads research efforts at the Fuels Research Laboratory at LANL, which has multiple inert glove box lines to handle and fabricate many oxygen sensitive compounds, such as UN, UC, U-Si, composite systems, ThN, as well as actinide bearing oxides. Dr. White has a Ph.D., M.S. and B.S. from the Colorado School of Mines in Golden Colorado. He currently has 26 refereed journal articles in the area of nuclear fuels synthesis and characterization and has mentored or co-mentored 14 graduate students, postdocs, and early career staff members.
"Assessment and Planning of HFIR Test Articles" , Joshua White, , Scarlett Widgeon Paisner, [2025] · DOI: 10.2172/2530337 | |
"Accelerated Irradiation and Qualification of Ceramic Nuclear Fuels" Joshua White, Meagan Wheeler, Scarlett Widgeon Paisner, [2024] · DOI: 10.2172/2448299 | |
"DISCOVARY PROJECT: Material Background Report" Joshua White, Scarlett Widgeon Paisner, [2024] · DOI: 10.2172/2447734 | |
"Uranium Mononitride (UN) Handbook" Alex Levinsky, Galen Craven, Vedant Mehta, Massimiliano Fratoni, Joshua White, Anders Andersson, Maria Kosmidou, Adrien Terricabras, Zachary Miller, [2024] · DOI: 10.2172/2440180 | |
"X-ray Analysis of Actinides using hiRx [Slides]" Bryan Hunter, Nikolaus Cordes, Joshua White, Arjen van Veelen, Brian Patterson, [2023] · DOI: 10.2172/2205019 | |
"Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels" Fabiola Cappia, Joshua T. White, Kenneth J. McClellan, Jason M. Harp, William A. Hanson, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154346 | |
"U-rich U-Mo Solidus, Liquidus, Enthalpy, and Thermal Diffusivity" Kara Luitjohan, Raymond Sandoval, Gabrielle Kral, Joshua White, Eric Tegtmeier, Kevin Bohn, Seth Imhoff, [2023] · DOI: 10.2172/1922011 | |
"2022 Accomplishments Report Template" Joshua White, Scarlett Paisner, Darrin Byler, Adrien Terricabras, [2022] · DOI: 10.2172/1889923 | |
"Refinement of UC/UO2 composites sintering update [Slides]" Joshua White, Scarlett Widgeon Paisner, [2022] · DOI: 10.2172/1870628 | |
"Documenting Development of Processing Parameters for Fabrication of Doped and Undoped Fuel Pellets (Summary Report)" Joshua White, Tarik Saleh, Tashiema Ulrich, Amber Telles, John Dunwoody, [2020] · DOI: 10.2172/1669074 | |
"High Temperature Moderator Material for Microreactors [Slides]" Erik Luther, Alexander Long, Theresa Cutler, Travis Grove, Vedant Mehta, Michael Cooper, Joshua White, Tarik Saleh, Joseph Wermer, Holly Trellue, Aditya Shivprasad, [2020] · DOI: 10.2172/1602731 | |
"Progress towards waterproofing uranium nitride" Joshua White, Amber Telles, Aditya Shivprasad, [2019] · DOI: 10.2172/1561054 | |
"Understanding the U3Si2 crystal structure evolution as a function of temperature by neutron diffraction and simulation" Elizabeth Sooby Wood, Tashiema Ulrich, Joshua White, Anders Andersson, Sven Vogel, [2019] · DOI: 10.2172/1559959 | |
"Report on waterproofing of UN studies" Amber Telles, Joshua White, Aditya Shivprasad, [2019] · DOI: 10.2172/1565797 | |
"Assessment of Hydriding in the U-Si System" Joseph Wermer, Joshua White, Aditya Shivprasad, [2019] · DOI: 10.2172/1544658 | |
"Development of and initial assessment of microstructurally engineered UN" Christopher Grote, Joshua White, Aditya Shivprasad, [2019] · DOI: 10.2172/1544659 | |
"Processing and Characterization of U3Si2 at the MiniFuel Scale" Joshua White, Najeb Abdul-Jabbar, [2019] · DOI: 10.2172/1532691 | |
"Assessment of thermophysical property characterization of MiniFuel scale geometries" Christopher Grote, Joshua White, Najeb Abdul-Jabbar, [2019] · DOI: 10.2172/1544665 | |
"Report on Current Assessment of Fabrication Routes to Large-Scale UN Production" Joshua White, Blake Nolen, Joseph Wermer, Nicholas Wozniak, [2019] · DOI: 10.2172/1497994 | |
"Crystal Structure Evolution of U-Si Nuclear Fuel Phases as a Function of Temperature" Tashiema Wilson, Joshua White, Sven Vogel, [2018] · DOI: 10.2172/1469500 | |
"Determination of elastic properties of polycrystalline U |
|
"Enthalpy of formation of U |
|
"Mechanical Properties of Uranium Silicides by Nanoindentation and Finite Elements Modeling" M. S. Elbakhshwan, N. A. Mara, J. T. White, A. T. Nelson, U. Carvajal-Nunez, [2018] JOM · DOI: 10.1007/s11837-017-2667-1 · EID: 2-s2.0-85036563101 | |
"Oxidation Kinetics of Ferritic Alloys in High-Temperature Steam Environments" Josh White, Peter Hosemann, Andrew Nelson, Stephen S. Parker, [2018] JOM · DOI: 10.1007/s11837-017-2639-5 · EID: 2-s2.0-85032802241 | |
"U |
|
"Corrigendum to “Thermophysical properties of U |
|
"Fabrication and thermophysical property characterization of UN/U |
|
"Oxidation behavior of U-Si compounds in air from 25 to 1000 C" J.T. White, A.T. Nelson, E. Sooby Wood, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.12.016 · EID: 2-s2.0-85006860828 | |
"The effect of aluminum additions on the oxidation resistance of U |
|
"Fabrication of advanced accident tolerant U-si fuel forms" [2016] Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance · EID: 2-s2.0-85019030092 | |
"Nanoscale mechanical behavior of uranium silicide compounds" [2016] Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance · EID: 2-s2.0-85019016906 | |
"State of knowledge and challenges of U-Si compounds for use in light water reactor accident tolerant fuel designs" [2016] Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance · EID: 2-s2.0-85019040644 | |
"The synthesis and air oxidation behavior of U-Si-Al and USi- B compositions" [2016] Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance · EID: 2-s2.0-85019038350 | |
"Thermophysical properties of USi to 1673 K" A.T. Nelson, J.T. Dunwoody, D.D. Byler, K.J. McClellan, J.T. White, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.01.013 · EID: 2-s2.0-84957000407 | |
"Measurements of the liquidus surface and solidus transitions of the NaCl-UCl<inf>3</inf> and NaCl-UCl<inf>3</inf>-CeCl<inf>3</inf> phase diagrams" A.T. Nelson, J.T. White, P.M. McIntyre, E.S. Sooby, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.07.050 · EID: 2-s2.0-84939824479 | |
"Thermodynamic assessment of the oxygen rich U-Ce-O system" S. Hirooka, T. Murakami, K. Suzuki, J.T. White, S.L. Voit, A.T. Nelson, B.W. Slone, T.M. Besmann, K.J. McClellan, M. Kato, J.W. McMurray, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.10.008 · EID: 2-s2.0-84946962589 | |
"Thermophysical properties of U |
|
"Thermophysical properties of U |
|
"Overview of properties and performance of uranium-silicide compounds for light water reactor applications" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84904649333 | |
"Oxidation resistance of uranium-silicide bearing composites for advanced nuclear reactor applications LA-UR 14-20517" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84904640643 | |
"Superparamagnetic nickel particles in yttria-stabilized zirconia prepared by reduction of Pechini-derived solution" Ivar E. Reimanis, James R. O’Brien, Joshua T. White, [2014] Journal of Nanoparticle Research · DOI: 10.1007/s11051-014-2426-y · EID: 2-s2.0-84901300240 | |
"Thermal expansion, heat capacity, and thermal conductivity of nickel ferrite (NiFe Nickel ferrite (NiFe2O4) is a major constituent of the corrosion deposits formed on the exterior of nuclear fuel cladding tubes during operation. NiFe2O4 has attracted much recent interest, mainly due to the impact of these deposits, known as CRUD, on the operation of commercial nuclear reactors. Although advances have been made in modeling CRUD nucleation and growth under a wide range of conditions, the thermophysical properties of NiFe2O4 at high temperatures have only been approximated, thereby limiting the accuracy of such models. In this study, samples of NiFe2O4 were synthesized to provide the thermal diffusivity, specific heat capacity, and thermal expansion data from room temperature to 1300 K. These results were then used to determine thermal conductivity. Numerical fits are provided to facilitate ongoing modeling efforts. The Curie temperature determined through these measurements was in slight disagreement with literature values. Transmission electron microscopy investigation of multiple NiFe2O4 samples revealed that minor nonstoichiometry was likely responsible for variations in the Curie temperature. However, these small changes in composition did not impact the thermal conductivity of NiFe2O4, and thus are not expected to play a large role in governing reactor performance. |
|
"Thermophysical properties of U |
|
"Thermal conductivity of UO |
|
"Internal reduction of Ni2+in ZrO The internal reduction of |
|
"Solubility of NiO in pechini-derived ZrO |
|
"The enhanced stabilization of the cubic phase in yttria-stabilized zirconia with the addition of nickel oxide"
Ivar E. Reimanis, Sophie Menzer, Grover Coors, Josh White,
[2011]
Journal of the American Ceramic Society
· DOI: 10.1111/j.1551-2916.2010.04349.x
· EID: 2-s2.0-79960275051
|
|
"Conductivity degradation of NiO-containing 8YSZ and 10YSZ electrolyte during reduction" J.R. O'Brien, J.T. White, W.G. Coors, [2009] Solid State Ionics · DOI: 10.1016/j.ssi.2008.12.004 · EID: 2-s2.0-60349085861 | |
Source: ORCID/CrossRef using DOI |
In-situ TEM Characterization of surrogate oxides microstructure under fission gas retention and reactor-relevant temperatures using ion beam implantation - FY 2024 RTE 2nd Call, #24-4972
Irradiation performance of defective Uranium Mononitride: The role of impurities in the defect accumulation using in-situ TEM ion irradiation - FY 2024 RTE 1st Call, #24-4846
Elucidating the Effect of Radiation-Induced Defect Accumulation on Swelling in UN using in-situ TEM Irradiation - FY 2023 RTE 1st Call, #23-4552
Elevated Temperature In-situ Scanning Electron Microscopy Microcantilever Testing of U3Si2 - FY 2019 RTE 2nd Call, #19-1793
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
Privacy and Accessibility · Vulnerability Disclosure Program