B. Forget

发表

Preliminary Coupling of the Monte Carlo Code OpenMC and the Multiphysics Object-Oriented Simulation Environment for Analyzing Doppler Feedback in Monte Carlo Simulations

Benoit Forget, Kord Smith, Derek Gaston, 2017 .

Physics-informed reinforcement learning optimization of nuclear assembly design

N. Roy, J. Joseph, B. Forget, 2020, Nuclear Engineering and Design.

SOLVING EIGENVALUE RESPONSE MATRIX EQUATIONS WITH JACOBIAN-FREE NEWTON-KRYLOV METHODS

Jeremy A. Roberts, B. Forget, 2011 .

Bond graph representation of nuclear reactor point kinetics and nearly incompressible thermal hydraulics

B. Forget, E. Sosnovsky, 2014 .

Calculation of adjoint-weighted reactor kinetics parameters in OpenMC

B. Forget, Kord Smith, Xingjie Peng, 2019, Annals of Nuclear Energy.

Development of continuous-energy sensitivity analysis capability in OpenMC

B. Forget, Kord Smith, Xingjie Peng, 2017 .

Monte Carlo power iteration: Entropy and spatial correlations

Benoit Forget, Kord Smith, Andrea Zoia, 2016 .

Bond graphs for spatial kinetics analysis of nuclear reactors

Benoit Forget, Eugeny Sosnovsky, B. Forget, 2013 .

Using the Neutron Excess Concept to Determine Starting Fuel Requirements for Minimum Burnup Breed-and-Burn Reactors

B. Forget, C. Forsberg, R. Petroski, 2011 .

Verification of MOCkingbird, an Unstructured-Mesh, Method of Characteristics Implementation Using the MOOSE Multiphysics Framework

D. Gaston, B. Forget, Kord Smith, 2017 .

Neutronic Analysis Capabilities for Conversion of the MIT Reactor to LEU Fuel

B. Forget, T. Gerrity, E. Wilson, 2012 .

Generation of the windowed multipole resonance data using Vector Fitting technique

B. Forget, Kord Smith, Kan Wang, 2018 .

Fast Reactor Alternative Studies: Effects of Transuranic Groupings on Metal and Oxide Sodium Fast Reactor Designs

Samuel E. Bays, R. Ferrer, B. Forget, 2007 .

Summary Report on New Transmutation Analysis for the Evaluation of Homogeneous and Heterogeneous Options in Fast Reactors

B. Forget, S. Bays, M. Pope, 2008 .

Importance of the (n,gamma) Cm-247 Evaluation on Neutron Emission in Fast Reactor Fuel Cycle Analysis

B. Forget, M. Asgari, R. Ferrer, 2007 .

On the Convergence of the Eigenvalue Response Matrix Method

Matthew S. Everson, Jeremy A. Roberts, B. Forget, 2015 .

Efficient MC–CMFD multiphysics

B. Forget, S. Harper, K. Smith, 2022, Annals of Nuclear Energy.

Neutron Cross Section Processing Methods for Improved Integral Benchmarking of Unresolved Resonance Region Evaluations

B. Forget, Kord Smith, F. Brown, 2016 .

Progress on the Implementation and Testing of OnThe-Fly Doppler Broadening for Monte Carlo Simulations

B. Forget, J. Walsh, C. Josey, 2015 .

Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor

B. Forget, E. Losa, M. Kostal, 2015 .

Demonstration of On-the-Fly Generation of Unresolved Resonance Region Cross Sections in a Monte Carlo Transport Code

B. Forget, Kord Smith, F. Brown, 2014 .

Ionospheric closure of small-scale Birkeland currents

B. Forget, J. Berthelier, J. Cerisier, 1991 .

An analysis of condensation errors in multi-group cross section generation for fine-mesh neutron transport calculations

B. Forget, Kord Smith, William Boyd, 2018 .

Cumulative migration method for computing rigorous diffusion coefficients and transport cross sections from Monte Carlo

B. Forget, Kord Smith, J. Ortensi, 2018 .

An energy recondensation method using the discrete generalized multigroup energy expansion theory

B. Forget, Lei Zhu, 2011 .

Implementation of a Full P1 Method in the Diffusion Code DONJON/NDF

B. Forget, J. Koclas, 2004 .

IMPROVED THERMAL SCATTERING DATA PREPARATION

B. Forget, J. Conlin, A. J. Trainer, 2021, EPJ Web of Conferences.

Improving variance convergence rate in monte carlo eigenvalue simulations via delayed neutrons

B. Forget, Kord Smith, Jilang Miao, 2020 .

Correlation diagnosis method for heterogeneous Monte Carlo eigenvalue simulations based on a diffusion approximation

B. Forget, Kord Smith, Jilang Miao, 2019, Annals of Nuclear Energy.

MIT Open Access Articles Progress and Status of the Openmc Monte Carlo Code

B. Forget, Kord Smith, P. Romano, 2022 .

Direct , onthe-fly calculation of unresolved resonance region cross sections in Monte Carlo simulations

B. Forget, Kord Smith, J. Walsh, 2017 .

Consortium for Advanced Simulation of LWRs CASL-U-2015-0179-000 Direct , Onthe-Fly Calculation of Unre olved Resonance Region Cross Sections in Monte Carlo Simulations

B. Forget, Kord Smith, J. Walsh, 2015 .

Direct, on-the-fly calculation of unresolved resonance region cross sections in Monte Carlo simulations

B. Forget, Kord Smith, F. Brown, 2015 .

Generalized Equivalence Theory Used with Spatially Linear Sources in the Method of Characteristics for Neutron Transport

B. Forget, Kord Smith, G. Giudicelli, 2020 .

An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part II: Flux and Eigenvalue Sensitivities to Nuclear Cross Sections and Resonance Parameters

B. Ganapol, B. Forget, V. Sobes, 2021, Nuclear Science and Engineering.

A generalized optimization methodology for isotope management

Benoit Forget, Mark Massie, B. Forget, 2010 .

Windowed multipole for cross section Doppler broadening

Benoit Forget, Kord Smith, Colin Josey, 2015, J. Comput. Phys..

OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development

Paul K. Romano, Benoit Forget, Kord Smith, 2014, ICS 2014.

Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh

Logan H. Harbour, D. Gaston, B. Forget, 2021, Nuclear Technology.

Full core 3D simulation of the BEAVRS benchmark with OpenMOC

Kord Smith, Benoit Forget, Geoffrey Gunow, 2019 .

Kriging-based algorithm for nuclear reactor neutronic design optimization

Benoit Forget, Lin-Wen Hu, Stephanie A. Kempf, 2012 .

Accelerated sampling of the free gas resonance elastic scattering kernel

Benoit Forget, Kord Smith, Jonathan A. Walsh, 2014 .

Neutronic characteristics of linear-assembly breed-and-burn reactors

Benoit Forget, Charles W. Forsberg, Robert C. Petroski, 2012 .

Direct Comparison of High-Order/Low-Order Transient Methods on the 2D-LRA Benchmark Problem

B. Forget, Kord Smith, Miriam A. Kreher, 2021, Nuclear Science and Engineering.

The “virtual density” theory of neutronics

Mark S. C. Reed, B. Forget, Kord Smith, 2018 .

The OpenMC Monte Carlo particle transport code

Benoit Forget, Paul K. Romano, B. Forget, 2012 .

Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor

Benoit Forget, Evžen Losa, Sterling Harper, 2016 .

The windowed multipole formalism and applications to uncertainty quantification

Benoit Forget, Kord Smith, Vladimir Sobes, 2021 .

Progress and status of the OpenMC Monte Carlo code

Andrew Siegel, Paul K. Romano, Benoit Forget, 2013 .

A fission-fusion hybrid reactor in steady-state L-mode tokamak configuration with natural uranium

B. Forget, R. Parker, M. Reed, 2012 .

Multigroup diffusion preconditioners for multiplying fixed-source transport problems

Benoit Forget, Jeremy A. Roberts, B. Forget, 2014, J. Comput. Phys..

2D full-core Monte Carlo pin-by-pin burnup calculations with the RMC code

Benoit Forget, Ding She, Jingang Liang, 2014 .

Development of burnup methods and capabilities in Monte Carlo code RMC

Paul K. Romano, Benoit Forget, Kord Smith, 2013 .

Resonance Parameter Adjustment Based on Integral Experiments

Benoit Forget, Luiz C Leal, Vladimir Sobes, 2016 .

Monte Carlo domain decomposition for robust nuclear reactor analysis

Andrew Siegel, Kord Smith, Nicholas Horelik, 2014, Parallel Comput..

Resonance Scattering Treatment with the Windowed Multipole Formalism

B. Forget, T. Burke, G. Ridley, 2023, 2303.08196.

Performance Analysis of a Reduced Data Movement Algorithm for Neutron Cross Section Data in Monte Carlo Simulations

Andrew R. Siegel, Benoit Forget, John R. Tramm, 2014, EASC.

A simple method for rejection sampling efficiency improvement on SIMT architectures

Benoit Forget, Gavin Ridley, B. Forget, 2021, Stat. Comput..

Modelling of the HTR-PM Pebble-bed Reactor using OpenMC

B. Forget, D. She, J. Yu, 2020, Transactions of the American Nuclear Society - Volume 122.

An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part III: Uncertainty Propagation and Multigroup Covariance Matrices

B. Forget, V. Sobes, A. Alhajri, 2023, Nuclear Science and Engineering.

Converting point-wise nuclear cross sections to pole representation using regularized vector fitting

Benoit Forget, Kord Smith, Jingang Liang, 2017, Comput. Phys. Commun..

On-the-fly doppler broadening of unresolved resonance region cross sections via probability band interpolation

Benoit Forget, Kord Smith, Forrest B. Brown, 2016 .

Optimizations of the energy grid search algorithm in continuous-energy Monte Carlo particle transport codes

Paul K. Romano, Benoit Forget, Kord Smith, 2015, Comput. Phys. Commun..

Windowed multipole sensitivity to target accuracy of the optimization procedure

Benoit Forget, Kord Smith, Colin Josey, 2015 .

Direct Doppler broadening in Monte Carlo simulations using the multipole representation

Benoit Forget, Kord Smith, B. Forget, 2014 .

Verification of depletion capability of OpenMC using VERA depletion benchmark

B. Forget, Jiankai Yu, 2022, Annals of Nuclear Energy.

Feasibility of a multigroup Boltzmann–Fokker–Planck solution for electron beam dose calculations

B. Forget, J. Carrier, P. Romano, 2023, Scientific Reports.

A single-step framework to generate spatially self-shielded multi-group cross sections from Monte Carlo transport simulations

B. Forget, Kord Smith, William Boyd, 2019, Annals of Nuclear Energy.

Neutron Interactions and Applications(pdf)

Benoit Forget, B. Forget, 2010 .

Benchmark for evaluation and validation of reactor simulations (BEAVRS)

Benoit Forget, Kord Smith, Nicholas Horelik, 2013 .

Heterogeneous Recycling in Fast Reactors

Benoit Forget, Steven J. Piet, Michael J. Driscoll, 2012 .

Predicting spatially dependent reaction rate for problem with nonuniform temperature distribution by subgroup method

Benoit Forget, Kord Smith, Liangzhi Cao, 2018 .

Large-scale design optimisation of boiling water reactor bundles with neuroevolution

Benoit Forget, Majdi I. Radaideh, Koroush Shirvan, 2021 .

Challenges in the development of high-fidelity LWR core neutronics tools

Benoit Forget, Kord Smith, B. Forget, 2013 .

Improved diffusion coefficients generated from Monte Carlo codes

Benoit Forget, Kord Smith, Bryan Herman, 2013 .

Calculation of multi-group migration areas in deterministic transport simulations

Kord Smith, Zhaoyuan Liu, Benoit Forget, 2020 .

The OpenMOC method of characteristics neutral particle transport code

Benoit Forget, Kord Smith, Lulu Li, 2014 .

Light Water Breeding with Nitride Fuel

M. Kazimi, B. Forget, E. Shwageraus, 2011 .

Verification of the 3D Method of characteristics solver in OpenMOC

Geoffrey Alexander Gunow, Benoit Forget, Kord Smith, 2016 .

Accuracy and Performance of 3D MOC for Full-Core PWR Problems

Benoit Forget, B. Forget, Samuel Shaner, 2017 .

Solving eigenvalue response matrix equations with nonlinear techniques

Jeremy A. Roberts, B. Forget, 2014 .

Feasibility of Breeding in Hard Spectrum Boiling Water Reactors with Oxide and Nitride Fuels

Mujid S. Kazimi, Benoit Forget, M. Kazimi, 2011 .

Tetris-inspired detector with neural network for radiation mapping

Engineering, Cambridge, Department of Materials Science, 2023, ArXiv.

Using Generalized Basis for Functional Expansion

Benoit Forget, Kord Smith, Zhuoran Han, 2021, Journal of Nuclear Engineering.

Windowed multipole representation of R -matrix cross sections

B. Forget, V. Sobes, Jin'gang Liang, 2020, 2010.10585.

Normalizing flows for thermal scattering sampling

B. Forget, A. Alhajri, 2022, Annals of Nuclear Energy.

A Three Dimensional Heterogeneous Coarse Mesh Transport Method for Reactor Calculations

Benoit Forget, B. Forget, 2006 .

Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code

Paul K. Romano, Benoit Forget, Kord Smith, 2019, Nuclear Technology.

Generalized equivalence methods for 3D multi-group neutron transport

B. Forget, Kord Smith, G. Giudicelli, 2018 .

Improvements of the CMFD acceleration capability of OpenMOC

B. Forget, Kord Smith, Wenbin Wu, 2020 .

Analysis of correlations and their impact on convergence rates in Monte Carlo eigenvalue simulations

Benoit Forget, Kord Smith, Jilang Miao, 2016 .

Simple benchmark for evaluating self-shielding models

Kord Smith, Benoit Forget, Nathan A Gibson, 2015 .

A Discrete Generalized Multigroup Energy Expansion Theory

B. Forget, Lei Zhu, 2010 .

Generalized Energy Condensation Theory

Benoit Forget, Farzad Rahnema, Steven Douglass, 2008 .

Stabilization of multi-group neutron transport with transport-corrected cross-sections

B. Forget, Kord Smith, Geoffrey Gunow, 2019, Annals of Nuclear Energy.

The Source Equivalence Acceleration Method

Matthew S. Everson, B. Forget, 2015 .

ARRC: A random ray neutron transport code for nuclear reactor simulation

Andrew Siegel, Benoit Forget, Kord Smith, 2018 .

The Random Ray Method for neutral particle transport

Andrew R. Siegel, John R. Tramm, Benoit Forget, 2017, J. Comput. Phys..

A task-based parallelism and vectorized approach to 3D Method of Characteristics (MOC) reactor simulation for high performance computing architectures

Andrew R. Siegel, Kord Smith, John R. Tramm, 2016, Comput. Phys. Commun..

Data decomposition of Monte Carlo particle transport simulations via tally servers

Andrew R. Siegel, Paul K. Romano, Benoit Forget, 2013, J. Comput. Phys..

The effect of load imbalances on the performance of Monte Carlo algorithms in LWR analysis

Andrew R. Siegel, Kyle G. Felker, Paul K. Romano, 2012, J. Comput. Phys..

Reducing 3D MOC Storage Requirements with Axial On-the-fly Ray Tracing

Geoffrey Alexander Gunow, Benoit Forget, Kord Smith, 2016 .

Impact of Including Higher Actinides in Fast Reactor Transmutation Analyses

Samuel E. Bays, R. Ferrer, B. Forget, 2007 .

“Virtual density” and traditional boundary perturbation theories: Analytic equivalence and numeric comparison

Mark S. C. Reed, B. Forget, Kord Smith, 2018 .

2-DIMENSIONAL PWR AND BWR WHOLE CORE BENCHMARK PROBLEMS

Benoit Forget, Farzad Rahnema, Steven Douglass, 2009 .

OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development

C. Calvin, Nicholas E. Horelik, Bryan R. Herman, 2014, ICS 2014.

Progress toward Monte Carlo–thermal hydraulic coupling using low-order nonlinear diffusion acceleration methods

Benoit Forget, Kord Smith, Bryan Herman, 2015 .

Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations

Paul K. Romano, Benoit Forget, B. Forget, 2012 .

Frequency Transform Method for Transient Analysis of Nuclear Reactors in Monte Carlo

B. Forget, Kord Smith, S. Shaner, 2022, Nuclear Science and Engineering.

High order methods for the integration of the Bateman equations and other problems of the form of y′ = F(y, t)y

Benoit Forget, Kord Smith, Colin Josey, 2017, J. Comput. Phys..

Using Fractional Cascading to Accelerate Cross Section Lookups in Monte Carlo Neutron Transport Calculations

Paul K. Romano, Benoit Forget, Colin Josey, 2015 .

Calculating Resonance Parameter Sensitivity Coefficients in SCALE

B. Forget, V. Sobes, C. Perfetti, 2017 .

The eﬀect of load imbalances on the performance of Monte Carlo codes in LWR analysis

A. Siegel, B. Forget, P. Romano, 2012 .

On the use of tally servers in Monte Carlo simulations of light-water reactors

Andrew Siegel, Paul K. Romano, Benoit Forget, 2014, ICS 2014.

Towards Scalable Parallelism in Monte Carlo Particle Transport Codes Using Remote Memory Access

Paul K. Romano, Benoit Forget, Forrest B. Brown, 2011 .