Jake A Hirschhorn

R&D Associate Staff Member - Nuclear Fuels Analyst

Dr. Hirschhorn received his B.S. in Nuclear Engineering from the Pennsylvania State University in 2016 and his Ph.D. in Materials Science and Engineering from the University of Florida in 2019. His graduate and postdoctoral research involved developing multiscale models for metallic and cermet-type nuclear fuels. Dr. Hirschhorn joined Oak Ridge National Laboratory in 2020. His current work involves developing fuel performance benchmarks and maintaining associated resources in support of the Versatile Test Reactor Project. He spends his free time riding his bike on the local trails, traveling to new places, and backpacking. 

Other Publications

Hirschhorn, J. A., Hilty, F. W., Tonks, M. R., & Rosales, J. (2021) Review and Preliminary Investigation into Fuel Loss from Cermets Composed of Uranium Nitride and a Molybdenum-Tungsten Alloy for Nuclear Thermal Propulsion Using Mesoscale Simulations. Journal of the Minerals, Metals & Materials Society, 1-16.
Hirschhorn, J. A., Tonks, M. R., & Matthews, C. (2021). A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON. Journal of Nuclear Materials, 544, 1-12.
Tonks, M. R., Simon, P. A., & Hirschhorn, J. A. (2021). Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel. Journal of Nuclear Materials, 543, 1-12.
Aitkaliyeva, A., Tonks, M. R., Hirschhorn, J. A., Powers, J. J., Greenquist, I. T., & Beeler, B. W. (2020). Research needs for uranium-zirconium-based metallic fuels. Office of Scientific and Technical Information, 1-32.
Aitkaliyeva, A., Adkins, C. A., McKinney, C., Hirschhorn, J. A., & Tonks, M. R. (2020). In search of theta-(Pu,Zr) in binary Pu-Zr: thermal and microstructural analyses of Pu-30Zr alloy. Journal of Nuclear Materials, 528, 1-7.
Hirschhorn, J. A., Tonks, M. R., Aitkaliyeva, A., & Adkins, C. A. (2020). Reexamination of a U-Zr diffusion couple experiment using quantitative phase-field modeling and sensitivity analysis. Journal of Nuclear Materials, 529, 1-13.
Hirschhorn, J. A., Tonks, M. R., Aitkaliyeva, A., & Adkins, C. A. (2019). A study of constituent redistribution in U-Zr fuels using quantitative phase-field modeling and sensitivity analysis. Journal of Nuclear Materials, 523, 143-156.
Aitkaliyeva, A., Adkins, C. A., Hirschhorn, J. A., McKinney, C., Tonks, M. R., & Di Lemma, F. G. (2019). Microstructural characterization of the as-cast and annealed Pu-10Zr alloy. Journal of Nuclear Materials, 523, 80-90.
Hirschhorn, J. A., Aitkaliyeva, A., Adkins, C. A., & Tonks, M. R. (2019). The microstructure and thermodynamic properties of U-24Pu-15Zr: Unexpected results and recommendations for U-Pu-Zr fuel research methodology. Journal of Nuclear Materials, 518, 80-94.
Hirschhorn, J. A., Tonks, M. R., Aitkaliyeva, A., & Adkins, C. A. (2019). Development and verification of a phase-field model for the equilibrium thermodynamics of U-Pu-Zr. Annals of Nuclear Energy, 124, 490-502.
Hirschhorn, J. A., Madsen, M., Mastroberardino, A., & Siddique, J. I. (2016). Magnetohydrodynamic boundary layer slip flow and heat transfer of power law fluid over a flat plate. Journal of Applied Fluid Mechanics, 9(1), 11-17.