• C/C++11
  • Python
  • CUDA
  • MATLAB
  • git
  • LaTeX

About Me

I am an R&D Associate Staff Member at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. I work in the Radiation Transport 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

Selected Publications

  1. E. Biondo, G. Davidson, T. Pandya, S. Hamilton, T. Evans, “Deterministically Estimated Fission Source Distributions for Monte Carlo k-Eigenvalue Problems,” Annals of Nuclear Energy, Vol. 119, pp. 7-22, 2018. [link]
  2. 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. [link]
  3. 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. [link]
  4. E. Biondo, P. Wilson, “Application of the Multi-Step CADIS Method to Fusion Energy Systems Analysis,” International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, South Korea, 2017.
  5. E. Biondo, A. Ibrahim, S. Mosher, R. Grove. “Accelerating Fusion Reactor Neutronics Modeling by Automatic Coupling of Hybrid Monte Carlo/Deterministic Transport on CAD Geometry.” Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method (ANS MC2015), Nashville, TN, 2015.