About Me

I am an R&D Staff Member at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. I work in the HPC Methods for Nuclear Applications Group, as a developer of the Shift Monte Carlo radiation transport code. I develop, implement, and analyze new methods for improving the performance and accuracy of nuclear reactor simulations on leadership-class supercomputers.
I grew up in the D.C. metro area, before attending the University of Minnesota where I double majored in chemical engineering and chemistry. As an undergraduate I worked as a process engineering intern at Polar Semiconductor Inc. and conducted research in synthetic organic chemistry in the Noland Research Group. It was during my junior year that I was first exposed to scientific computing in a numerical methods course and also became interested in nuclear energy as a way to mitigate climate change.
These interests lead me to join the Computational Nuclear Engineering Research Group at the University of Wisconsin, where I earned my Ph.D. in nuclear engineering. As a graduate student, I had coursework in advanced mathematics, numerical methods, algorithms, and high-performance computing. I gained nuclear engineering analysis experience performing calculations in support of the SHINE Medical Technologies medical isotope facility. My software development skills matured as a leading contributor to the Python for Nuclear Engineering Toolkit and as an intern at ORNL working on the ADVANTG code. My dissertation research focused on optimizing Monte Carlo simulations for biological dose rate calculations for nuclear fusion reactors by approximating the nuclear transmutation process.

Contact Details

elliott.biondo@gmail.com
veb@ornl.gov

Publication Highlights

  • E. Biondo, T. Evans, S. Johnson, S. Hamilton, "Comparison of Nested Geometry Treatments within GPU-Based Monte Carlo Neutron Transport Simulations of Fission Reactors," International Journal of High Performance Computing Applications, submitted March, 2024.
  • E. Biondo, G. Davidson, B. Ade, "Layered CAD/CSG geometry for spatially complex radiation transport scenarios," Annals of Nuclear Energy, Vol. 181, 2023.
    Published document | Open-access manuscript
  • E. Biondo, T. Evans, G. Davidson, S. Hamilton, "Singular Value Decomposition of Adjoint Flux Distributions for Monte Carlo Variance Reduction," Annals of Nuclear Energy, Vol. 141, 2020.
    Published document | Open-access manuscript
  • E. Biondo, P. Wilson, “Transmutation Approximations for the Application of Hybrid Monte Carlo/Deterministic Neutron Transport to Shutdown Dose Rate Analysis," Nuclear Science and Engineering, Vol. 187, Issue 1, pp. 27-48, 2017.
    Published document | Open-access manuscript
  • E. Biondo, A. Davis, P. Wilson, “Shutdown Dose Rate Analysis with CAD Geometry, Cartesian/Tetrahedral Mesh, and Advanced Variance Reduction," Fusion Engineering and Design, Vol. 106, pp. 77–84, 2016.
    Published document