Pierre-Clément Simon

Profile Information
Name
Dr. Pierre-Clément Simon
Institution
Idaho National Laboratory
Position
Computational Materials Scientist
h-Index
ORCID
0000-0001-7083-2628
Biography

Pierre-Clément (PC) Simon joined INL as a computational materials scientist in March 2021. Pierre-Clément works with the Bison group and the lower length scale group at INL to develop multi-scale, multi-physics approaches. He applies his expertise to understand nuclear materials behavior in a variety of systems such as LWRs, advanced reactors, and fusion reactors.

Prior to joining INL, PC graduated from The Pennsylvania State University with a Ph.D. in Nuclear Engineering under the supervision of Dr. Motta and Dr. Tonks in 2021. Before that, he obtained an M.Sc. in Engineering Science from the Ecole Centrale de Lyon in France in 2018, an M.Sc. in Nuclear Engineering from The Pennsylvania State University in 2017, and a B.Sc. in Applied Mathematics from the University Claude Bernard de Lyon in France in 2014.

Expertise
BISON, Computational Materials, Fission Gas, Grain Structure, Hydrides, LWR, Marmot, Mesoscale Modeling, Modeling, MOOSE, Multiscale Modeling, Zirconium
Publications:
"Integrated multiscale experiment and model analysis of radially resolved microstructure and thermal conductivity in mixed oxide fuel" Joshua Ferrigno, Tsvetoslav Pavlov, Pierre-Clément Simon, Ethan Hisle, Stephen Novascone, Fabiola Cappia, Marat Khafizov, Journal of Nuclear Materials Vol. 609 2025 Link
Additional Publications:
"Toward a high-fidelity tritium transport modeling for retention and permeation experiments" Pierre-Clément A. Simon, Casey T. Icenhour, Gyanender Singh, Masashi Shimada, [2024] Fusion Engineering and Design · DOI: 10.1016/j.fusengdes.2024.114438 · ISSN: 0920-3796
"An integrated statistical-thermodynamic model for fission gas release and swelling in nuclear fuels" Nathan A. Capps, Michael W.D. Cooper, Pierre-Clément A. Simon, Brian D. Wirth, Charles K.C. Lieou, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154869 · ISSN: 0022-3115
"Mechanisms of Mesoscale Hydride Morphology and Reorientation in a Polycrystal Investigated Using Phase-Field Modeling" Long-Qing Chen, Mark R. Daymond, Arthur T. Motta, Michael R. Tonks, Pierre-Clément A. Simon, [2023] · DOI: 10.1520/stp164520220069

This study focuses on the precipitation of nanoscale hydrides in polycrystalline zirconium as a first step to predicting the hydride morphology observed experimentally and investigating the mechanisms responsible for hydride reorientation at the mesoscale. A quantitative phase-field model, which includes the elastic anisotropy of the nanoscale zirconium hydride system, is developed to investigate the mechanism of hydride reorientation in which the presence of an applied hoop stress promotes hydride precipitation in grains with basal poles aligned with the circumferential direction. Although still elongated along the basal plane of the hexagonal matrix, nanoscale hydrides growing in grains oriented perpendicular to the applied stress appear radial at the mesoscale. Thus, a preferential hydride precipitation in grains with basal poles aligned parallel to the applied stress could account for mesoscale hydride reorientation. This mechanism is consistent with experimental observations performed in other studies.

"Empirical and mechanistic transient fission gas release model for high-burnup LOCA conditions" Larry Aagesen, David Andersson, Oliver Baldwin, W. Cade Brinkley, Michael W.D. Cooper, Jason Harp, Stephen Novascone, Pierre-Clément A. Simon, Christopher Matthews, Brian D. Wirth, Nathan Capps, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154557
"Compare predictions of transient fission gas release by empirical and mechanistic models to experiments in high burnup UO2 fuel" Larry Aagesen, Jr., Nathan Capps, Michael Cooper, Kyle Gamble, Logan Harbour, Christopher Matthews, Stephen Novascone, Daniel Schwen, Brian Wirth, Pierre-Clement Simon, [2023] · DOI: 10.2172/2203701
"Multi-scale fission product release model with comparison to AGR data" Larry Aagesen, Jr., Chaitanya Bhave, Chao Jiang, Wen Jiang, Jia-Hong Ke, Lin Yang, Pierre-Clement Simon, [2023] · DOI: 10.2172/2203700
"Tritium Transport Modeling at the Pore Scale in Ceramic Breeder Materials Using TMAP8" Paul W. Humrickhouse, Alexander D. Lindsay, Pierre-Clement A. Simon, [2022] IEEE Transactions on Plasma Science · DOI: 10.1109/tps.2022.3183525
"Implementation and testing of physics-based pulverization model in BISON" Sudipta Biswas, Kyle Gamble, Wen Jiang, Pierre-Clément Simon, Benjamin Spencer, Larry Aagesen, Jr., [2022] · DOI: 10.2172/1984930
"Mechanistic calculation of the effective silver diffusion coefficient in polycrystalline silicon carbide: Application to silver release in AGR-1 TRISO particles" Larry K. Aagesen, Chao Jiang, Wen Jiang, Jia-Hong Ke, P.-C.A. Simon, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153669
"Predicting the hydride rim by improving the solubility limits in the Hydride Nucleation-Growth-Dissolution (HNGD) model" Pierre-Clément A. Simon, Arthur T. Motta, Florian Passelaigue, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153363 · ISSN: 0022-3115
"Investigation of δ zirconium hydride morphology in a single crystal using quantitative phase field simulations supported by experiments" Larry K. Aagesen, Andrea M. Jokisaari, Long-Qing Chen, Mark R. Daymond, Arthur T. Motta, Michael R. Tonks, P.-C.A. Simon, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153303 · ISSN: 0022-3115
"Atomistic and mesoscale simulations to determine effective diffusion coefficient of fission products in SiC" Jia-Hong Ke, Pierre-Clement Simon, Wen Jiang, Larry Aagesen, Jr., Chao Jiang, [2021] · DOI: 10.2172/1825508
"Zirconium Hydride Precipitation and Dissolution Kinetics in Zirconium Alloys" Pierre-Clément A. Simon, Arthur T. Motta, Jonathan D. Almer, Evrard Lacroix, [2021] · DOI: 10.1520/stp162220190035

Hydride precipitation may impact the integrity of zirconium-based nuclear fuel cladding, both during normal operation and during extended dry storage. To better understand such degradation, a study of hydride precipitation of zirconium hydrides in Zircaloy-4 samples was performed. The samples were submitted to various thermomechanical cycles using both in situ synchrotron X-ray diffraction and differential scanning calorimetry. Results showed that as the hydrided samples were cooled at moderate to fast cooling rates, the hydrogen content in solid solution (CSS) decreased, following the terminal solid solubility for precipitation (TSSP) curve, reflecting hydride precipitation in the matrix. However, when the samples were held for an isothermal anneal at a fixed temperature, the CSS continued to decrease below TSSP and approached the terminal solid solubility for dissolution (TSSD). This result suggests that TSSP is a kinetic limit and that a unique solubility limit TSSD governs zirconium hydride precipitation. Hydride precipitation rate and the degree of precipitation reaction completion between 280 and 350°C were obtained using differential scanning calorimetry. Using this data, a temperature-time transformation diagram for hydride precipitation in Zircaloy-4 was generated that showed that hydride precipitation is diffusion-driven under 310°C and reaction-driven above 310°C. The experimental data were fitted to the Johnson-Mehl-Avrami-Kolmogorov model and an Avrami parameter of 2.56 was obtained (2.5 is the theoretical value for the growth of platelets). Results imply that hydride nucleation occurs if CSS is greater than TSSP while hydride growth occurs if preexisting hydride platelets are present and CSS is above TSSD. Combined with existing theory, these data were used to develop the hydride growth, nucleation, and dissolution model that can simulate hydrogen behavior in Zircaloy.

"Quantifying the effect of hydride microstructure on zirconium alloys embrittlement using image analysis" Cailon Frank, Long-Qing Chen, Mark R. Daymond, Michael R. Tonks, Arthur T. Motta, Pierre-Clément A. Simon, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152817
"Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel" Pierre-Clément A. Simon, Jacob Hirschhorn, Michael R. Tonks, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152576
"The effects of introducing elasticity using different interpolation schemes to the grand potential phase field model" Larry K. Aagesen, Arthur T. Motta, Michael R. Tonks, Pierre-Clément A. Simon, [2020] Computational Materials Science · DOI: 10.1016/j.commatsci.2020.109790
"Hydrogen in zirconium alloys: A review" Laurent Capolungo, Long-Qing Chen, Mahmut Nedim Cinbiz, Mark R. Daymond, Donald A. Koss, Evrard Lacroix, Giovanni Pastore, Pierre-Clément A. Simon, Michael R. Tonks, Brian D. Wirth, Mohammed A. Zikry, Arthur T. Motta, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.02.042
Source: ORCID/CrossRef using DOI