Adrien Terricabras

Profile Information
Name
Dr. Adrien Terricabras
Institution
Los Alamos National Laboratory
Position
Postdoctoral Research Associate
h-Index
1
ORCID
0000-0002-9054-0144
Biography

Dr. Adrien J. Terricabras is currently a postdoctoral research associate at Los Alamos National Laboratory. He is conducting research on the impact of processing and fabrication methods on nuclear fuel properties and microstructure on both UN-based ceramic-metal composite (CerMet) fuels and UO2-based ceramic-ceramic (CerCer) fuels. He obtained his PhD in Energy Science and Engineering at the University of Tennessee with Dr. Steven Zinkle as primary advisor. His doctoral research focused on ion irradiation effects on advanced nuclear fuels, specifically on high thermal conductivity nuclear fuel surrogates and nitride coatings for coated particle fuels application. He graduated with an A.S. in Materials Science and Engineering from the Nîmes Institute of Technology (France), studied Chemical Engineering during his third year at the University of the West of Scotland (UK) and received a M.S. in Radiochemistry and Nuclear Materials Science from the University of Montpellier (France).


Expertise
Accident Tolerant Fuel, Ceramic Fuel, Composites, Ion Irradiation, Li-ion, LWR, Nanoindentation, Nuclear Fuel, Nuclear Materials, SEM, XRD
Additional Publications:
"Comprehensive defect evaluation of advanced nuclear fuels using high-resolution acoustic signals and optimized sensor separation" Sangmin Lee, Rajendra P. Palanisamy, Adrien J. Terricabras, Jacqe Jansen van Vuuren, Danie Jacobs, Renoux Kritzinger, Timothy P. Coons, Alp T. Findikoglu, Do-Kyung Pyun, [2026] NDT & E International · DOI: 10.1016/j.ndteint.2025.103502
"Chromium doping effects on UO2 grain boundary chemistry: A combined experimental and modeling approach" Conor O.T. Galvin, Maria Kosmidou, Miguel Pena, Arjen van Veelen, William D. Neilson, Shen J. Dillon, Michael W.D. Cooper, David A. Andersson, Sarah C. Finkeldei, Joshua T. White, Adrien J. Terricabras, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2025.156114
"Nucleation Rate Controlled Grain Boundary and Lattice Creep" Joshua T. White, Jordan Brown, Dawei Zhang, Adrien J. Terricabras, Jian Luo, Khalid Hattar, Sarah Finkeldei, Shen Dillon, D. Keith Coffman, [2025] Acta Materialia · DOI: 10.1016/j.actamat.2025.121485
"Challenges in Explicit Modeling of TRISO in MCNP" , , , Theresa Cutler, Michael Rising, Kristin Stolte, Adrien Terricabras, , Peter Brain, [2025] · DOI: 10.2172/2572528
"Temperature dependency of dislocation evolution in Kr-irradiated Uranium mononitride (UN) through in-situ TEM observation and modeling" Christopher Matthews, Adrien J. Terricabras, Hi T. Vo, Wei-Ying Chen, Joshua T. White, Caitlin A. Kohnert, Darrin D. Byler, David A. Andersson, Michael W.D. Cooper, Erofili Kardoulaki, Maria Kosmidou, [2025] Acta Materialia · DOI: 10.1016/j.actamat.2025.120824
"High-temperature structure, elasticity, and thermal expansion of ε-ZrH1.8" Christopher A. Mizzi, Daniel A. Rehn, Tyler Smith, Scarlett Widgeon Paisner, Adrien J. Terricabras, Darren M. Parkison, Sven C. Vogel, Caitlin A. Kohnert, Mathew L. Hayne, Thomas J. Nizolek, M.A. Torrez, Tannor T.J. Munroe, Boris Maiorov, Tarik A. Saleh, Aditya P. Shivprasad, James R. Torres, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155437
"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
"Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2" Sean M. Drewry, Keri Campbell, Elizabeth J. Judge, Darrin D. Byler, Emily S. Teti, Arjen van Veelen, Scarlett Widgeon Paisner, Joshua T. White, Adrien J. Terricabras, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155022
"Finite temperature properties of uranium mononitride" Daniel A. Rehn, Adrien J. Terricabras, Arjen van Veelen, Michael W.D. Cooper, Scarlett Widgeon Paisner, Sven C. Vogel, Joshua T. White, David A. Andersson, Vancho Kocevski, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154241
"2022 Accomplishments Report Template" Joshua White, Scarlett Paisner, Darrin Byler, Adrien Terricabras, [2022] · DOI: 10.2172/1889923
"Thermal conductivity evaluation of ion irradiated Si3N4 and ZrN ceramics using spatial domain thermoreflectance" Joshua Ferrigno, Ling Wang, Marat Khafizov, Andrew T. Nelson, Steven J. Zinkle, Adrien J. Terricabras, [2022] Journal of Applied Physics · DOI: 10.1063/5.0099175

Nitride ceramics have been investigated for different applications in the nuclear industry, such as space nuclear power, fusion reactor diagnostics and plasma heating, inert matrix fuels, and accident tolerant fuels. Although thermal conductivity remains one of the most important properties to track following irradiation, traditional techniques such as laser flash and xenon flash are limited to bulk sample characterization, which requires lengthy and cost-consuming neutron irradiation. This work used spatial domain thermoreflectance (SDTR) for the micrometer-scale measurement of thermal conductivity in 15 MeV Ni ion-irradiated silicon nitride and zirconium nitride from 1 to 50 dpa and 300 to 700 °C. The SDTR-measured unirradiated thermal conductivity was found to be consistent with the published data on bulk samples. Electrically conductive ZrN exhibits modest reduction after irradiation which is minimal at the highest irradiation temperatures. In electrically insulating Si3N4, the reduction is more significant and unlike ZrN, the reduction remains significant even at a higher irradiation temperature. The thermal resistance evolution following irradiation was compared with lattice swelling, which was determined using grazing incidence x-ray diffraction, and radiation-induced defects were observed using transmission electron microscopy. A saturation value was observed between 15 and 50 dpa for thermal conductivity degradation in both nitride ceramics and a direct correlation with high-temperature defect recombination was observed, as well as the potential presence of additional carrier scattering mechanisms.

"Properties and microstructure evolution of silicon nitride and zirconium nitride following Ni ion irradiation" Ling Wang, Alicia M. Raftery, Andrew T. Nelson, Steven J. Zinkle, Adrien J. Terricabras, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153643
"Characterization of high thermal conductivity fuel surrogates before and after ion irradiation" James O. Kiggans, Ling Wang, Steven J. Zinkle, Adrien J. Terricabras, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153027
Source: ORCID/CrossRef using DOI