Publications

Publications

Journal Publications

FOR A FULL LIST, SEE GOOGLE SCHOLAR

I. Abdallah, T. Kim, X. Wu, L. Bailly-Salins, M. Elbakhshwan, M. Carroll, M.R. Tonks, J.H. Perepezko, A. Couet, Oxidation kinetics and microstructure evolution of high Mn stainless-steel alloy in CO2 at 700 °C, Corrosion Science. 195 (2022) 110013.
 
P.-C.A. Simon, L.K. Aagesen, A.M. Jokisaari, L.-Q. Chen, M.R. Daymond, A.T. Motta, M.R. Tonks, Investigation of δ zirconium hydride morphology in a single crystal using quantitative phase field simulations supported by experiments, Journal of Nuclear Materials. 557 (2021) 153303.
 
L. Shi, M. Sessim, M.R. Tonks, S.R. Phillpot, High-temperature oxidation of carbon fiber and char by molecular dynamics simulation, Carbon. 185 (2021) 449–463. 
 
 
A.A. Rezwan, A.M. Jokisaari, M.R. Tonks, Modeling brittle fracture due to anisotropic thermal expansion in polycrystalline materials, Computational Materials Science. 194 (2021) 110407. 
 
S. Zhang, D.-U. Kim, W. Jiang, M.R. Tonk, A phase field model of crack propagation in anisotropic brittle materials with preferred fracture planes, Computational Materials Science. 193 (2021) 110400.
 
 
P.-C.A. Simon, C. Frank, L.-Q. Chen, M.R. Daymond, M.R. Tonks, A.T. Motta, Quantifying the effect of hydride microstructure on zirconium alloys embrittlement using image analysis, Journal of Nuclear Materials. 547 (2021) 152817.
 
F.W. Hilty, D.-U. Kim, M.R. Tonks, Impact of fission gas bubbles on thermal conductivity of UO2 fuels with high thermal conductivity additives, Journal of Nuclear Materials. 546 (2021) 152779. 
 
I. Greenquist, M. Tonks, Y. Zhang, Analysis of the impact of fuel microstructure on irradiation-enhanced densification using grand potential simulations, Annals of Nuclear Energy. 151 (2021) 107858.
 
M.R. Tonks, P.-C.A. Simon, J. Hirschhorn, Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel, Journal of Nuclear Materials. 543 (2021) 152576.
 

F.W. Hilty, M.R. Tonks, Development and application of a microstructure dependent thermal resistor model for UO2 reactor fuel with high thermal conductivity additives, Journal of Nuclear Materials. 540 (2020) 152334. 

P-C.A. Simon, L.K. Aagesen, A.T. Motta, M.R. Tonks, The effects of introducing elasticity using different interpolation schemes to the grand potential phase field model, Computational Materials Science. 183 (2020) 109790.

A. Rezwan, M.R. Tonks, M.P. Short, Evaluations of the performance of multi-metallic layered composite cladding for the light water reactor accident tolerant fuel, Journal of Nuclear Materials. (2020) 152136, 1–13.

W. Noble, M.R. Tonks, S.P. Fitzgerald, Turing Instability in the Solid State: Void Lattices in Irradiated Metals, Phys. Rev. Lett. 124 (2020) 167401, 1–6.

A. Cheniour, M.R. Tonks, B. Gong, T. Yao, L. He, J.M. Harp, B. Beeler, Y. Zhang, J. Lian, Development of a grain growth model for U3Si2 using experimental data, phase field simulation and molecular dynamics, Journal of Nuclear Materials. 532 (2020) 152069, 1–26.

I. Greenquist, M. Tonks, M. Cooper, D. Andersson, Y. Zhang, Grand potential sintering simulations of doped UO2 accident-tolerant fuel concepts, Journal of Nuclear Materials. (2020) 152052, 1–28.

J. Hirschhorn, M. Tonks, A. Aitkaliyeva, C. Adkins, Reexamination of a U-Zr diffusion couple experiment using quantitative phase-field modeling and sensitivity analysis, Journal of Nuclear Materials. 529 (2020) 151929, 1–13.

I. Greenquist, M.R. Tonks, L.K. Aagesen, Y. Zhang, Development of a microstructural grand potential-based sintering model, Computational Materials Science. 172 (2020) 109288, 1–15.

Zhang, W. Jiang, M.R. Tonks, A new phase field fracture model for brittle materials that accounts for elastic anisotropy, Computer Methods in Applied Mechanics and Engineering. 358 (2020) 112643, 1–15.

A. Aitkaliyeva, C.A. Adkins, C. McKinney, J. Hirschhorn, M.R. Tonks, In search of θ-(Pu,Zr) in binary Pu–Zr: Thermal and microstructural analyses of Pu − 30Zr alloy, Journal of Nuclear Materials. 528 (2020) 151875, 1–8.

J. Hirschhorn, M.R. Tonks, A. Aitkaliyeva, C. Adkins, A study of constituent redistribution in U–Zr fuels using quantitative phase-field modeling and sensitivity analysis, Journal of Nuclear Materials. 523 (2019) 143–156.

A. Aitkaliyeva, C.A. Adkins, J. Hirschhorn, C. McKinney, M.R. Tonks, F.G. Di Lemma, Microstructural characterization of the as-cast and annealed Pu-10Zr alloy, Journal of Nuclear Materials. 523 (2019) 80–90.

M.R. Tonks, L.K. Aagesen, The Phase Field Method: Mesoscale Simulation Aiding Material Discovery, Annual Review of Materials Research. 49 (2019) 79–102.

J. Hirschhorn, A. Aitkaliyeva, C. Adkins, M. Tonks, The microstructure and thermodynamic behavior of as-cast U-24Pu-15Zr: Unexpected results and recommendations for U-Pu-Zr fuel research methodology, Journal of Nuclear Materials. 518 (2019) 80–94.

J. Hirschhorn, M. Tonks, A. Aitkaliyeva, C. Adkins, Development and verification of a phase-field model for the equilibrium thermodynamics of U-Pu-Zr, Annals of Nuclear Energy. 124 (2019) 490–502.

I. Greenquist, M.R. Tonks, Y. Zhang, Review of sintering and densification in nuclear fuels: Physical mechanisms, experimental results, and computational models, Journal of Nuclear Materials. 507 (2018) 381–395.

M.R. Tonks, A. Cheniour, L. Aagesen, How to apply the phase field method to model radiation damage, Computational Materials Science. 147 (2018) 353–362.

NEWS

“SINTERING AND DENSIFICATION IN NUCLEAR POWER”, SCIENCE TRENDS