Search Results - "Romano, Paul"
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OpenMC: A state-of-the-art Monte Carlo code for research and development
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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Development and validation of fully open-source R2S shutdown dose rate capabilities in OpenMC
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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Upsampling Monte Carlo Reactor Simulation Tallies in Depleted Sodium-Cooled Fast Reactor Assemblies Using a Convolutional Neural Network
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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Extending deterministic transport capabilities for very-high and ultra-high energy electron beams
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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Upsampling Monte Carlo reactor simulation tallies in depleted LWR assemblies fueled with LEU and HALEU using a convolutional neural network
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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An algorithm for generating random variates from the Madland–Nix fission energy spectrum
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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Hardware-Accelerated Ray Tracing of CAD-Based Geometry for Monte Carlo Radiation Transport
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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Upsampling Monte Carlo neutron transport simulation tallies using a convolutional neural network
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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Feasibility of a multigroup Boltzmann–Fokker–Planck solution for electron beam dose calculations
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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Data decomposition of Monte Carlo particle transport simulations via tally servers
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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Methods for processing and use of thermal neutron scattering data in OpenMC
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 -
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Language and design evolution of the OpenMC Monte Carlo particle transport code
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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The Effect of the Flux Separability Approximation on Multigroup Neutron Transport
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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Optimizations of the energy grid search algorithm in continuous-energy Monte Carlo particle transport codes
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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Nuclear data processing capabilities in OpenMC
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 -
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Performance Portable Monte Carlo Particle Transport on Intel, NVIDIA, and AMD GPUs
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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Celeritas: Accelerating Geant4 with GPUs
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 -
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TOWARDS CAD-BASED GEOMETRY MODELLING WITH THE RANDOM RAY METHOD
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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A COMPARISON OF STOCHASTIC MESH CELL VOLUME COMPUTATION STRATEGIES FOR THE RANDOM RAY METHOD OF NEUTRAL PARTICLE TRANSPORT
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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Comparison of algorithms for Doppler broadening pointwise tabulated cross sections
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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