Search Results - "Romano, Paul"

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  1. 1

    OpenMC: A state-of-the-art Monte Carlo code for research and development by Romano, Paul K., Horelik, Nicholas E., Herman, Bryan R., Nelson, Adam G., Forget, Benoit, Smith, Kord

    Published in Annals of nuclear energy (01-08-2015)
    “…•OpenMC is an open source Monte Carlo particle transport code.•Solid geometry and continuous-energy physics allow high-fidelity simulations.•Development has…”
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    Journal Article
  2. 2

    Development and validation of fully open-source R2S shutdown dose rate capabilities in OpenMC by Peterson, Ethan E., Romano, Paul K., Shriwise, Patrick C., Myers, Patrick A.

    Published in Nuclear fusion (01-05-2024)
    “…We present the first fully open-source capabilities for shutdown dose rate (SDR) calculations of fusion energy facilities based on the Rigorous 2-Step (R2S)…”
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    Journal Article
  3. 3

    Upsampling Monte Carlo Reactor Simulation Tallies in Depleted Sodium-Cooled Fast Reactor Assemblies Using a Convolutional Neural Network by Berry, Jessica, Romano, Paul, Osborne, Andrew

    Published in Energies (Basel) (01-05-2024)
    “…The computational demand of neutron Monte Carlo transport simulations can increase rapidly with the spatial and energy resolution of tallied physical…”
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    Journal Article
  4. 4

    Extending deterministic transport capabilities for very-high and ultra-high energy electron beams by Naceur, Ahmed, Bienvenue, Charles, Romano, Paul, Chilian, Cornelia, Carrier, Jean-François

    Published in Scientific reports (02-02-2024)
    “…Focused Very-High Energy Electron (VHEE, 50–300 MeV) and Ultra-High Energy Electron (UHEE, > 300 MeV) beams can accurately target both large and deeply seated…”
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    Journal Article
  5. 5

    Upsampling Monte Carlo reactor simulation tallies in depleted LWR assemblies fueled with LEU and HALEU using a convolutional neural network by Berry, Jessica, Romano, Paul, Osborne, Andrew

    Published in AIP advances (01-01-2024)
    “…Simulating nuclear reactor cores at the highest achievable spatial and energy resolution is critical in modeling these systems accurately. Increasing the…”
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    Journal Article
  6. 6

    An algorithm for generating random variates from the Madland–Nix fission energy spectrum by Romano, Paul K.

    Published in Computer physics communications (01-02-2015)
    “…An algorithm for generating random variates from the Madland–Nix fission energy spectrum assuming a constant compound nucleus cross section is given based on…”
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    Journal Article
  7. 7

    Hardware-Accelerated Ray Tracing of CAD-Based Geometry for Monte Carlo Radiation Transport by Shriwise, Patrick C., Wilson, Paul P. H., Davis, Andrew, Romano, Paul K.

    Published in Computing in science & engineering (01-03-2022)
    “…Monte Carlo radiation transport (MCRT) methods have been used to simulate radiation environments for many decades by tracking individual particles through a…”
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    Journal Article
  8. 8

    Upsampling Monte Carlo neutron transport simulation tallies using a convolutional neural network by Osborne, Andrew, Dorville, Joffrey, Romano, Paul

    Published in Energy and AI (01-07-2023)
    “…•A residual convolutional neural network model was trained to upsample nuclear reactor simulations' neutron flux tallies from 64 × 64 pixels and 8 energy…”
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    Journal Article
  9. 9

    Feasibility of a multigroup Boltzmann–Fokker–Planck solution for electron beam dose calculations by Naceur, Ahmed, Hébert, Alain, Romano, Paul, Forget, Benoit, Chilian, Cornelia, Carrier, Jean-François

    Published in Scientific reports (24-01-2023)
    “…Legacy nuclear-reactor Boltzmann solvers start clinical deployment as an alternative to Monte Carlo (MC) codes and Fermi–Eyges semiemprical models in radiation…”
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    Journal Article
  10. 10

    Data decomposition of Monte Carlo particle transport simulations via tally servers by Romano, Paul K., Siegel, Andrew R., Forget, Benoit, Smith, Kord

    Published in Journal of computational physics (01-11-2013)
    “…An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is developed, analyzed, and implemented in a continuous-energy…”
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    Journal Article
  11. 11

    Methods for processing and use of thermal neutron scattering data in OpenMC by Romano, Paul K., Nelson, Adam G.

    Published in EPJ Web of conferences (2023)
    “…OpenMC, an open source Monte Carlo particle transport code, relies on its own nuclear data format that is based on the HDF5 file format. The Python API within…”
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    Journal Article Conference Proceeding
  12. 12

    Language and design evolution of the OpenMC Monte Carlo particle transport code by Romano, Paul, Tramm, John, Shriwise, Patrick

    Published in EPJ nuclear sciences & technologies (05-11-2024)
    “…The OpenMC Monte Carlo particle transport code has been continuously developed for 13 years by a large community of contributors. In that time span, the…”
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    Journal Article
  13. 13

    The Effect of the Flux Separability Approximation on Multigroup Neutron Transport by Nelson, Adam G., Boyd, William, Romano, Paul K.

    Published in Journal of Nuclear Engineering (22-03-2021)
    “…The angular dependence of flux-weighted multigroup cross sections is commonly neglected when generating multigroup libraries. The error of this flux…”
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    Journal Article
  14. 14

    Optimizations of the energy grid search algorithm in continuous-energy Monte Carlo particle transport codes by Walsh, Jonathan A., Romano, Paul K., Forget, Benoit, Smith, Kord S.

    Published in Computer physics communications (01-11-2015)
    “…In this work we propose, implement, and test various optimizations of the typical energy grid-cross section pair lookup algorithm in Monte Carlo particle…”
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    Journal Article
  15. 15

    Nuclear data processing capabilities in OpenMC by Romano, Paul, Harper, Sterling

    Published in EPJ Web of conferences (01-01-2017)
    “…This work describes newly developed features of the OpenMC code for nuclear data processing. OpenMC, in addition to being a transport code, includes a rich,…”
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    Journal Article Conference Proceeding
  16. 16

    Performance Portable Monte Carlo Particle Transport on Intel, NVIDIA, and AMD GPUs by Tramm, John, Romano, Paul, Shriwise, Patrick, Lund, Amanda, Doerfert, Johannes, Steinbrecher, Patrick, Siegel, Andrew, Ridley, Gavin

    Published in EPJ Web of conferences (2024)
    “…OpenMC is an open source Monte Carlo neutral particle transport application that has recently been ported to GPU using the OpenMP target offloading model. We…”
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    Journal Article
  17. 17

    Celeritas: Accelerating Geant4 with GPUs by Johnson, Seth R., Esseiva, Julien, Biondo, Elliott, Canal, Philippe, Demarteau, Marcel, Evans, Thomas, Jun, Soon Yung, Lima, Guilherme, Lund, Amanda, Romano, Paul, Tognini, Stefano C.

    Published in EPJ Web of conferences (01-01-2024)
    “…Celeritas [1] is a new Monte Carlo (MC) detector simulation code designed for computationally intensive applications (specifically, High Lumi- nosity Large…”
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    Journal Article Conference Proceeding
  18. 18

    TOWARDS CAD-BASED GEOMETRY MODELLING WITH THE RANDOM RAY METHOD by Shriwise, Patrick C., Tramm, John R., Davis, Andrew, Romano, Paul K.

    Published in EPJ Web of conferences (01-01-2021)
    “…The Advanced Random Ray Code (ARRC) is a high performance computing application capable of high-fidelity simulations of full core nuclear reactor models. ARRC…”
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    Journal Article
  19. 19

    A COMPARISON OF STOCHASTIC MESH CELL VOLUME COMPUTATION STRATEGIES FOR THE RANDOM RAY METHOD OF NEUTRAL PARTICLE TRANSPORT by Tramm, John R., Siegel, Andrew R., Lund, Amanda L., Romano, Paul K.

    Published in EPJ Web of conferences (01-01-2021)
    “…The random ray method is a recently developed neutron transport method that can be used to perform efficient full-core, general-purpose, high-fidelity 3D…”
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    Journal Article
  20. 20

    Comparison of algorithms for Doppler broadening pointwise tabulated cross sections by Romano, Paul K, Trumbull, Timothy H

    Published in Annals of nuclear energy (01-01-2015)
    “…In this paper, three algorithms for Doppler broadening pointwise tabulated cross sections are compared on the basis of speed and accuracy. The use of a…”
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