Joshua White

Profile Information
Name
Dr. Joshua White
Institution
Los Alamos National Laboratory
Position
Research Staff
Affiliation
American Nuclear Society, American Ceramics Society
h-Index
10
ORCID
0000-0002-4409-2264
Biography

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.

Expertise
Accident Tolerant Fuel, Ceramic Fuel, Oxidation, Thermophysical Properties
Additional Publications:
"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 U3Si2using resonant ultrasound spectroscopy" T.A. Saleh, J.T. White, B. Maiorov, A.T. Nelson, U. Carvajal-Nunez, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.11.008 · EID: 2-s2.0-85034815483
"Enthalpy of formation of U3Si2: A high-temperature drop calorimetry study" Joshua T. White, Andrew T. Nelson, Artaches Migdisov, Robert Roback, Hongwu Xu, Xiaofeng Guo, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.04.032 · EID: 2-s2.0-85046171781
"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
"U3Si2behavior in H2O: Part I, flowing steam and the effect of hydrogen" J.T. White, C.J. Grote, A.T. Nelson, E. Sooby Wood, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.01.002 · EID: 2-s2.0-85040541273
"Corrigendum to “Thermophysical properties of U3Si2to 1773 K” [J. Nucl. Mater. (2015) 464 (275–280)] (S002231151500241X)(10.1016/j.jnucmat.2015.04.031)" A.T. Nelson, J.T. Dunwoody, D.J. Safarik, K.J. McClellan, J.T. White, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.11.015 · EID: 2-s2.0-85007420323
"Fabrication and thermophysical property characterization of UN/U3Si2composite fuel forms" A.W. Travis, J.T. Dunwoody, A.T. Nelson, J.T. White, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.08.041 · EID: 2-s2.0-85029047275
"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 U3Si2" J.T. White, A.T. Nelson, E. Sooby Wood, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.02.045 · EID: 2-s2.0-85016602381
"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 U3Si2to 1773 K" A.T. Nelson, J.T. Dunwoody, D.D. Byler, D.J. Safarik, K.J. McClellan, J.T. White, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.04.031 · EID: 2-s2.0-84929315700
"Thermophysical properties of U3Si5to 1773 K" A.T. Nelson, D.D. Byler, D.J. Safarik, J.T. Dunwoody, K.J. McClellan, J.T. White, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.10.021 · EID: 2-s2.0-84908348644
"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 (NiFe2O4)" Joshua T. White, David A. Andersson, Jeffery A. Aguiar, Kenneth J. McClellan, Darrin D. Byler, Michael P. Short, Christopher R. Stanek, Andrew T. Nelson, [2014] Journal of the American Ceramic Society · DOI: 10.1111/jace.12901 · EID: 2-s2.0-84900866385

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 U3Si to 1150 K" A.T. Nelson, D.D. Byler, J.A. Valdez, K.J. McClellan, J.T. White, [2014] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.05.037 · EID: 2-s2.0-84902190790
"Thermal conductivity of UO2+x and U4O9-y" A.T. Nelson, J.T. White, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.07.063 · EID: 2-s2.0-84883201327
"Internal reduction of Ni2+in ZrO2stabilized with 10 mol% Y2O3examined with VSM and SQUID magnetometry" Ivar E. Reimanis, Jianhua Tong, James R. O'Brien, Amy Morrissey, Joshua T. White, [2012] Journal of the American Ceramic Society · DOI: 10.1111/j.1551-2916.2012.05441.x · EID: 2-s2.0-84870932683

The internal reduction of Ni2+ ions dissolved in 10YSZ (10 percent by mole Y2O3‐ stabilized ZrO2) was studied using magnetometry. Chemical methods were used to produce specimens with varying amounts of NiO (0.01–11.8% by mol), below and above the solubility limit of NiO in 10YSZ. The solubility limit was determined using x‐ray diffraction measurements in which the change in lattice parameter was correlated to the amount of Ni2+ ions in solution. Vibrating sample magnetometry (VSM) was used to unequivocally establish that NiO does not exist as a second phase for specimen compositions less than or equal to 0.5 m/o NiO. Specimens with compositions 0.5, 0.1, and 0.01 m/o NiO in YSZ were then prepared and heat treated in Ar – 2% H2 at 1273 K for times ranging from 1 to 20 h. The ferromagnetic response of the reduced specimens was measured using SQUID magnetometry at 100 K to quantify the amount of Ni metal formed as a function of time. SQUID magnetometry measurements of the same specimens were performed at 5 K where the paramagnetic response may be used to quantify the decrease of Ni2+ ions during reduction. The two SQUID measurements agree well and revealed parabolic growth law kinetics. Transmission electron microscopy revealed that internal reduction in these specimens proceeds by the formation of Ni0 along the YSZ grain boundaries. The results indicate that there are two stages of internal reduction in polycrystalline NiO‐containing YSZ. For short times, precipitation of Ni occurs at grain‐boundary regions, and for longer times, it occurs inside the grains.

"Solubility of NiO in pechini-derived ZrO2examined with SQUID magnetometry" Ivar E. Reimanis, James R. O’Brien, Joshua T. White, [2012] Journal of Materials Science · DOI: 10.1007/s10853-011-5839-3 · EID: 2-s2.0-84857647298
"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

The influence of NiO on the stabilization and microstructure of yittria (Y2O3)‐stabilized zirconia (ZrO2) (YSZ) is examined. Cold‐pressed powders comprising varying amounts of NiO, 8 mol%Y2O3, and ZrO2 were sintered at 1500°C for 4 h. Specimens were subsequently given a 100 h heat treatment at 1500°C. Phase analysis by X‐ray diffraction revealed that the presence of NiO leads to a greater amount of cubic phase ZrO2 for the sintered specimens compared with the control specimens. The cubic ZrO2 lattice parameter was significantly smaller for specimens containing NiO, revealing that Ni2+ ions likely enter the cubic ZrO2 lattice and play a role in decreasing the time and temperature required for stabilization of the cubic phase. A spherical diffusion model was used to estimate the diffusion of Y3+ and Ni2+ into ZrO2. These results are discussed in the context of the role of NiO in the synthesis of YSZ.

"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