Publications

Summary

All publications are available on DSpace@MIT thanks to the MIT Faculty Open Access Policy, or under related publisher agreements.

Monte Carlo

Journal Publications

Xingjie Peng, Jingang Liang, Benoit Forget, Kord Smith, “ Calculation of adjoint-weighted reactor kinetics parameters in OpenMC ”, Annals of Nuclear Energy, 128, 231-235, 2019
Zhaoyuan Liu, Kord Smith, Benoit Forget, Javier Ortensi, “ Cumulative migration method for computing rigorous diffusion coefficients and transport cross sections from Monte Carlo ”, Annals of Nuclear Energy, 112, 507-516, 2018
Jilang Miao, Benoit Forget, Kord Smith, “ Predicting correlation coefficients for Monte Carlo eigenvalue simulations with multitype branching process ”, Annals of Nuclear Energy, 112, 307-321, 2018
William Boyd, Nathan Gibson, Benoit Forget, Kord Smith , “ An analysis of condensation errors in multi-group cross section generation for fine-mesh neutron transport calculations ”, Annals of Nuclear Energy, 112, 267-276, 2018
Xingjie Peng, Jingang Liang, Abdulla Alhajri, Benoit Forget, Kord Smith, “ Development of continuous-energy sensitivity analysis capability in OpenMC ”, Annals of Nuclear Energy, 110, 362-383, 2017
Matthew Ellis, Derek Gaston, Benoit Forget, Kord Smith, “ Preliminary Coupling of the Monte Carlo Code OpenMC and the Multiphysics Object-Oriented Simulation Environment for Analyzing Doppler Feedback in Monte Carlo Simulations ”, Nuclear Science and Engineering, 185, 184-193, 2017
M.Nowak, J.Miao, E.Dumonteil, B.Forget, A.Onillon, K.S.Smith, A.Zoia, “ Monte Carlo power iteration: Entropy and spatial correlations ”, Annals of Nuclear Energy, 94, 856-868, 2016
J.Miao, B.Forget, K.S.Smith, “ Analysis of correlations and their impact on convergence in Monte Carlo eigenvalue simulations ”, Annals of Nuclear Energy, 92, 81-95, 2016
M.Ellis, D.Gaston, B.Forget, K.Smith, “Preliminary Coupling of the Monte Carlo code OpenMC and the Multiphysics Object-Oriented Simulation Environment for Analyzing Doppler Feedback in Monte Carlo Simulations.” Nuclear Science and Engineering, 185-1 184-193, 2017.
M.Nowak, J.Miao, E.Dumonteil, B.Forget, A.Onillon, K.S.Smith, A.Zoia, “Monte Carlo power iteration: Entropy and spatial correlations,” Annals of Nuclear Energy, 94, 856-868, 2016.
J.Miao, B.Forget, K.S.Smith, “Analysis of correlations and their impact on convergence in Monte Carlo eigenvalue simulations,” Annals of Nuclear Energy, 92, 81-95, 2016.
B.R.Herman, B.Forget, K.Smith, “Progress towards Monte Carlo – Thermal Hydraulic Coupling using Low-Order Nonlinear Diffusion Acceleration Methods,” Annals of Nuclear Energy, special issue, 84, 63-72, 2015.
J.Roberts, M.Everson and B.Forget, “On the Convergence of the Eigenvalue Response Matrix Method,” Nuclear Science and Engineering, 181(3), 331-34, 2015.
J.Walsh, P.Romano, B.Forget, K.Smith, “Optimizations of the Energy Grid Search Algorithm in Continuous-Energy Monte Carlo Particle Transport Codes,” Computer Physics Communications, 196, Pages 134-142, 2015.
P.Romano, N.Horelik, B.Herman, A.Nelson, B.Forget, K.Smith, “OpenMC: A state-of-the-art Monte Carlo code for research and development,” Annals of Nuclear Energy, special issue, 82, 90-97, 2015.
N.Horelik, A.Siegel, B.Forget, K.Smith, “Monte Carlo domain decomposition for robust nuclear reactor analysis,” Parallel Computing, 40(10), pp646-660, 2014.
J. Walsh, B. Forget and K. Smith “Accelerated sampling of the free gas resonance elastic scattering kernel”, Annals of Nuclear Energy , 69, 116-124, 2014.
B.Forget, S.Xu, K.Smith, “Direct Doppler Broadening in Monte Carlo Simulations using the Multipole Representation,” Annals of Nuclear Energy, 64, 78-85, 2014.
D.She, J. Liang, K.Wang and B.Forget, “2D Full-Core Monte Carlo pin-by-pin Burnup Calculations with the RMC code,” Annals of Nuclear Energy, 64, 201-205, 2014.
A.Siegel, K.Smith, K.Felker, P.Romano, B.Forget and P.Beckman, “Improved cache performance in Monte Carlo transport calculations using energy banding,” Computer Physics Communications, 185(4), 1195-1199, 2014.
P.K. Romano, A.R. Seigel, B.Forget, K.Smith, “Data Decomposition of Monte Carlo particle transport simulations via tally servers,” J. Comp. Phys., 252, 1, 20-26, 2013
A.R.Siegel, K.Smith, P.K.Romano, B.Forget and K.Felker, “Multi-core Performance Studies of OpenMC,” International Journal of HPC Applications, doi:10.1177/1094342013492179, 2013
A.R. Seigel, K.Smith, P.K. Romano, B.Forget, K.Felker, “The effect of load imbalances on the performance of Monte Carlo codes in LWR analysis,” J. Comp. Phys., 235, 901-911, 2013.
P.K. Romano and B.Forget, “The OpenMC Monte Carlo Particle Transport Code,” Annals of Nuc. En. 51, 274-281, 2013.
D.She, Y.Liu, K.Wang, G.Yu, B.Forget, P.Romano and K.Smith, “Development of burnup methods and capabilities in Monte Carlo code RMC,” Annals of Nuc. En. 51, 289-294, 2013.
P.Romano and B.Forget, “Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations,” Nuclear Science and Engineering, 170 (2), 125-135, 2012.
P.Romano, B.Forget and F.Brown, “Towards Scalable Parallelism in Monte Carlo Particle Transport Codes Using Remote Memory Access” Progress in Nuclear Science and Technology, 2, 670-675 (2011)

Conference proceedings

Z. Han, Kord Smith, Benoit Forget, “ Performance Analysis of Zernike-based FETs on a 2D PWR Pin Cell ”, M&C 2019 Topical Meeting, Portland, 2019
S. Kumar, Kord Smith, Benoit Forget, “ Analysis of Fission Source Stationarity for a 3D SMR core using Functional Expansion Tallies ”, M&C 2019 Topical Meeting, Portland, 2019
J. Salcedo-Perez, Kord Smith, Benoit Forget, P. Romano “ Hybrid Tallies To Improve Performance in Depletion Monte Carlo Simulations ”, M&C 2019 Topical Meeting, Portland, 2019
S. Harper, P. Romano, Kord Smith, Benoit Forget, “ Efficient Dynamic Threadsafe Neighbor Lists for Monte Carlo Ray Tracing ”, M&C 2019 Topical Meeting, Portland, 2019
M. Kreher, Kord Smith, Benoit Forget, “ Single-Batch Monte Carlo Multiphysics Coupling ”, M&C 2019 Topical Meeting, Portland, 2019
P. Ducru, J. Liang, V. Sobes, A. Alhajri, I. Meyer, Kord Smith, Benoit Forget, “ Embedded Monte Carlo Neutron Random Walk and Uncertainty in Nuclear Cross Sections
”, M&C 2019 Topical Meeting, Portland, 2019
X.Peng, B.Forget, K.Smith, “ Calculation of Adjoint-Weighted Reactor Kinetics Parameters in OpenMC ”, PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, 2018
S.Harper, K.Smith, B.Forget, “ Faster Monte Carlo Multiphysics using Temperature Derivatives ”, PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, 2018
Z.Liu, K.Smith, B.Forget, “ Group-Wise Tally Scheme of Incremental Migration Area for Cumulative Migration Method ”, PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, 2018
Carl C. Haugen, Benoit Forget, Kord S. Smith, “ A Rejection Sampling Based Method for Determining Thermal Scattering Angle and Energy ”, M&C 2017 Topical Meeting, 2017
Zhaoyuan Liu, Kord Smith, Benoit Forget, “ Progress of Cumulative Migration Method for Computing Diffusion Coeffcients with OpenMC ”, M&C 2017 Topical Meeting, 2017
Travis J. Labossiere-Hickman, Benoit Forget, “ Selected VERA Core Physics Benchmarks in OpenMC ”, ANS Transactions, 117, 2017
Colin Josey, Kord Smith, Benoit Forget, “ A Stochastic Benchmark Problem for Depletion Algorithms ”, ANS Transactions, 117, 2017
M.S. Ellis, C. Josey, B. Forget, K. Smith, “Spatially Continuous Depletion Algorithm for Monte Carlo Simulations,” Transactions of the American Nuclear Society, 115, 2016.
J.Miao, B.Forget, K.Smith, “Predicting Correlation Coefficients for Monte Carlo Eigenvalue Simulations,” Transactions of the American Nuclear Society, 115, 2016.
L.Abel, W.Boyd, B.Forget, K.Smith, “Interactive Visualization of Multi-Group Cross Sections on High-Fidelity Spatial Meshes,” Transactions of the American Nuclear Society, 114, 2016.
M. Ellis, D. Gaston, B. Forget, and K. Smith, “Continuous Temperature Representation in Coupled OpenMC/MOOSE Simulations,” PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1-5, 2016.
Z. Liu, K. Smith, and B. Forget, “A Cumulative Migration Method for Computing Rigorous Transport Cross Sections and Diffusion Coefficients for LWR Lattices with Monte Carlo,” PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1-5, 2016.
Q.Shen, W.Boyd, B.Forget, K.Smith, “Tally Precision Triggers for the OpenMC Monte Carlo Code,” Transactions of the American Nuclear Society, 112, 637-640, 2015.
M.Ellis, D.Gaston, B.Forget, K.Smith, “Preliminary Coupling of the Monte Carlo code OpenMC and the Multiphysics Object Oriented Simulation Environment (MOOSE) for Analyzing Doppler Feedback in Monte Carlo Simulations,” M&C +SNA + MC 2015, Nashville, TN, April, 2015.
A.Lund, A.Siegel, B.Forget, C.Josey, P.Romano, “Using fractional cascading to accelerate cross section lookups in Monte Carlo neutron transport calculations,” M&C +SNA + MC 2015, Nashville, TN, April, 2015.
T.Viitanen, J.Leppanen, B.Forget, “Target Motion Sampling Temperature Treatment Technique with Track-Length Estimators in OpenMC – Preliminary Results,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
N.Horelik, B.Forget, K.S.Smith, A.Siegel, “Domain Decomposition and Terabyte Tallies with the OpenMC Monte Carlo Neutron Transport Code,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
W.Boyd, N.Gibson, S.Shaner, L.Li, J.Hunter, K.S.Smith, B.Forget, “PINSPEC: A Monte Carlo Code for Pin Cell Spectral Calculations for Educational Applications,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
B.R.Herman, B.Forget, K.S.Smith, P.K.Romano, T.M.Sutton, D.J.Kelly, B.N.Aviles, “Analysis of Tally Correlation in Large Light Water Reactors,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
J.Tramm, A.Siegel, C.Josey, B.Forget, “Performance Analysis of a Reduced Data Movement Algorithm for Neutron Cross Section Data in Monte Carlo Simulations”, Exascale Applications and Software Conference, Sweden, April, 2014.
J.A.Walsh, B.Forget and K.Smith, “Validation of OpenMC Reactor Physics Simulation with the B&W 1810 Series Benchmark,” American Nuclear Society – Winter Meeting, Washington, DC, November 2013.
B.Forget, "Preliminary Studies on the Resiliency of Stochastic Linear Solvers," Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, SNA + MC 2013, Paris, France, October 27-31, 2013
P.K.Romano, B.R.Herman, N.E.Horelik, A.G.Nelson, B.Forget, K.Smith, "OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development," Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, SNA + MC 2013, Paris, France, October 27-31, 2013.
P.K.Romano, B.Forget, K.Smith, "On the Use of Tally Servers in Monte Carlo Simulations of Light Water Reactors," Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, SNA + MC 2013, Paris, France, October 27-31, 2013
P.K.Romano, B.R.Herman, N.E.Horelik, B.Forget, K.Smith, A.Siegel "Progress and Status of the OpenMC Monte Carlo Code," International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013, Sun Valley, ID, May 5-9, 2013.
B.R.Herman, B.Forget, K.Smith, B.Aviles, "Improved Diffusion Coefficients Generated from Monte Carlo Codes," International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013, Sun Valley, ID, May 5-9, 2013.
P.Romano and B.Forget, “Reducing Parallel Communication in Monte Carlo Simulations via Batch Statistics,” Transactions of the American Nuclear Society, American Nuclear Society – Winter Meeting, San Diego, November 2012.
K.Smith, B.Forget, P.Romano, B.Herman and A.Siegel, “Challenges and Approaches to Coupled Monte Carlo Neutronic/Fluid Flow Analysis of Commercial Nuclear Reactors,” SIAM, Twelfth Copper Mountain Conference on Iterative Methods, March (2012)
P.Romano, B.Forget and F.Brown, “Towards Scalable Parallelism in Monte Carlo Particle Transport Codes Using Remote Memory Access” Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, October 17-21 (2010).

Deterministic methods

Journal Publications

Guillaume Giudicelli, Kord Smith, Benoit Forget, “ Generalized equivalence methods for 3D multi-group neutron transport ”, Annals of Nuclear Energy, 112, 9-16, 2018
Mark Reed, Kord Smith, Benoit Forget, “ Virtual density and traditional boundary perturbation theories: Analytic equivalence and numeric comparison ”, Annals of Nuclear Energy, 112, 531-548, 2018
Mark Reed, Kord Smith, Benoit Forget, “ The virtual density theory of neutronics ”, Annals of Nuclear Energy, 112, 549-596, 2018
John R. Tramm, Kord S. Smith, Benoit Forget, Andrew R. Siegel, “ ARRC: A random ray neutron transport code for nuclear reactor simulation ”, Annals of Nuclear Energy, 112, 693-714, 2018
Qingming He, Liangzhi Cao, Hongchun Wu, Benoit Forget, Kord Smith , “ Predicting spatially dependent reaction rate for problem with nonuniform temperature distribution by subgroup method ”, Annals of Nuclear Energy, 111, 188-203, 2018
C. Josey, B. Forget, K. Smith , “ High order methods for the integration of the Bateman equations and other problems of the form of y'=F(y;t)y ”, Journal of Computational Physics, 350, 296-313, 2017
John R. Tramm, Kord S. Smith, Benoit Forget, Andrew R. Siegel, “ The Random Ray Method for neutral particle transport ”, Journal of Computational Physics, 342, 229-252, 2017
J.Tramm, K.Smith, B.Forget, A.Siegel, “The Random Ray Method – A computationally efficient algorithm for 2D and 3D neutron transport enabling high fidelity nuclear reactor simulation,” Journal of Computational Physics, 342, 229-252, 2017.
W.Boyd, A.Siegel, B.Forget, K.Smith, “ Parallel Performance Results for the OpenMOC Neutron Transport Code on Multi-Core Platforms ”, International Journal of High Performance Computing Applications, pp. 360-375, 2016
J.Tramm, G.Gunow, T.He, K.Smith, B.Forget, A.Siegel, “A task-based parallelism and vectorized approach to 3D Method of Characteristics reactor simulation for high performance computing architectures,” Computer Physics Communications, 202, 141-150, 2016.
L.Li, K.Smith, B.Forget, R.Ferrer, “LOO: A Low-order Nonlinear Transport Scheme for Acceleration of Method of Characteristics,” Journal of Nuclear Science and Technology, PHYSOR 2014 Special Issue, 52, Issue 7-8, 2015.
M.Everson, B.Forget, “The Source Equivalence Acceleration Method,” Annals of Nuclear Energy, 76, 177-192, 2015.
J.Roberts and B.Forget, “Solving eigenvalue response matrix equations with nonlinear techniques,” Annals of Nuclear Energy, 69, 97-107, 2014.
J.Roberts and B. Forget, “Multigroup Diffusion Preconditioners for Multiplying Fixed-Source Transport Problems,” J. Comp. Phys., 274, 455-472, 2014.
W.Boyd, S.Shaner, L.Li, B.Forget and K.Smith, “The OpenMOC Method of Charactheristics Neutral Particle Transport Code”, Annals of Nuclear Energy, 68, 43-52, 2014.
E.Sosnovsky, B.Forget, “Bond Graph Representation of Nuclear Reactor Point Kinetics and Nearly Incompressible Thermal Hydraulics,” Annals of Nuclear Energy, 68, 15-29, 2014.
N.A.Gibson and B.Forget, “On the Stability of the Discrete Generalized Multigroup Method,” Annals of Nuclear Energy, 65, 421-432, 2014.
M.S.Everson and B.Forget, “Spatial Recondensation using the Discrete Generalized Multigroup Method,” Annals of Nuc En., 62, 487-498, 2013
E. Sosnovsky and B.Forget, “Introduction to Bond Graphs for Spatial Kinetics,” Annals of Nuc En., 56, 208-226, 2013.
L.Zhu and B.Forget, “An Energy Recondensation Method Using the Discrete Generalized Multigroup Energy Expansion Theory,” Annals of Nuclear Energy, 38 (2011).
L.Zhu and B.Forget, “A Discrete Generalized Multigroup Energy Expansion Theory,” Nucl. Sci. Eng., 166 (2010).

Conference proceedings

G.Giudicelli, K.Smith, B.Forget, “ Generalized Equivalence Theory used with Spatially Linear Sources in the Method of Characteristics for Neutron Transport ”, M&C 2019 Topical Meeting, Portland, 2019
G.Giudicelli, K.Smith, B.Forget, “ Generalized Equivalence Theory for Multi-Scale Equivalence in Assembly Transport Calculations ”, PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, 2018
J.Tramm, B.Forget, K.Smith, “ Early Experience in Full Core Reactor Simulation with the Random Ray method ”, PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, 2018
Geoffrey Gunow, Samuel Shaner, William Boyd, Benoit Forget, and Kord Smith, “ Accuracy and Performance of 3D MOC for Full-Core PWR Problems ”, M&C 2017 Topical Meeting, 2017
Derek R. Gaston, Benoit Forget, Kord S. Smith, “ Richard C. Martineau Verification of MOCkingbird an Unstructured-Mesh Method of Characteristics Implementation Using the MOOSE Multiphysics Framework ”, M&C 2017 Topical Meeting, 2017
Guillaume Giudicelli, Kord Smith, Benoit Forget, “ A New Polar Angle Dependent Equivalence Method for 3D Transport Calculations ”, ANS Transactions, 117, 2017
Qingming He, Liangzhi Cao, Hongchun Wu, Benoit Forget, Kord Smith, “ Treatment of Nonuniform Temperature Distribution by Subgroup Method ”, ANS Transactions, 116, 2017
G. Gunow, S. Shaner, B. Forget, K. Smith, “Reducing 3D MOC Storage Requirements with Axial On-the-Fly Ray Tracing,” PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1-5, 2016.
S. Shaner, G. Gunow, K. Smith, and B. Forget, “Verification of the 3D Method of Characteristics Solver in OpenMOC,” PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1-5, 2016.
W.Boyd, S.Shaner, B.Forget, K.Smith, “Program Optimization and Improved Workflow Synthesis for the OpenMOC Neutron Transport Code”, Transactions of the American Nuclear Society, 113, 78-81, 2015.
N.Gibson, B.Forget, “Mutual Self-Shielding in the Subgroup Method,” ICAPP 2015, Nices, France, May 2015.
L.Li, K.Smith, B.Forget, “Techniques for stabilizing Coarse-Mesh Finite Difference (CMFD) in Methods of Characteristics (MOC),” M&C +SNA + MC 2015, Nashville, TN, April, 2015.
N.Gibson, B.Forget, K.Smith, “Simple Benchmark for Evaluating Self-Shielding Models,” M&C +SNA + MC 2015, Nashville, TN, April, 2015.
G.Gunow, J.Tramm, B.Forget, K.Smith, T.He, “SimpleMOC - A Performance Abstraction for 3D MOC,” M&C +SNA + MC 2015, Nashville, TN, April, 2015.
W.Boyd, B.Forget, K.Smith, “OpenCG: A Combinatorial Geometry Modeling Tool for Data Processing and Code Verification,” M&C +SNA + MC 2015, Nashville, TN, April, 2015.
S.Shaner, G.Gunow, B.Forget, K.Smith, “Theoretical Analysis of Track Generation in 3D Method of Characteristics,” M&C +SNA + MC 2015, Nashville, TN, April, 2015.
L.Li, K.Smith, B.Forget, “A Low Order Nonlinear Transport Acceleration Scheme for the Method of Characteristics,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
D.Lax, W.Boyd, N.Horelik, B.Forget, K.Smith, “A Memory Efficient Algorithm for Classifying Unique Regions in Constructive Solid Geometries,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
G.A.Gunow, K.S.Smith, B.Forget, “LWR Fuel Reactivity Depletion Verification using Flux Map Data,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
W.Boyd, K.S.Smith, B.Forget, A.Siegel, “Parallel Performance Results for the OpenMOC Method of Characteristics Code on Multi-Core Platforms,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
S.Shaner, K.S.Smith, B.Forget, “Sensitivity Analysis and Performance of the Adiabatic, Theta and Multigrid Amplitude Function Kinetics Methods in 2D MOC Neutron Transport,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
M.Reed, K.S.Smith, and B.Forget, “The Virtual Density Theory of Neutronics: A Generic Method for Reactivity Coefficients due to Geometry Distortions,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
J.A.Roberts, R.L.Reed, B.Forget, “Phase Space Bases for Response Matrix Methods,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
M.Reed, K.Smith, B.Forget, “The “Virtual Density” Principle of Neutronics: Toward Rapid Computation of Reactivity Effects in Practical Core Distortion Scenarios,” International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013, Sun Valley, ID, May 5-9, 2013.
W.R.Boyd, K.Smith, B.Forget, "A Massively Parallel Method of Characteristic Neutral Particle Transport Code for GPUs," International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013, Sun Valley, ID, May 5-9, 2013.
N.Gibson and B.Forget, “Eliminating Flux Updates from the Discrete Generalized Multigroup Method,” Transactions of the American Nuclear Society, American Nuclear Society – Winter Meeting, San Diego, November 2012.
J.Roberts, B.Forget, “A Quadrature Set for a Method of Characteristics Response Matrix Method,” Transactions of the American Nuclear Society, Chicago, IL (2012)
M.Everson and B.Forget, “A 1D Analysis of Two High Order MOC Methods,” PHYSOR 2012 – Advances in Reactor Physics, Knoxville, Tennessee, USA, April 15-20, (2012)
N.Gibson and B.Forget, “Application of the Discrete Generalized Multigroup Method to Ultra-Fine Energy Mesh in Infinite Medium Calculations,” PHYSOR 2012 – Advances in Reactor Physics, Knoxville, Tennessee, USA, April 15-20, (2012)
J.Roberts and B.Forget, “Krylov Subspace Iteration for Eigenvalue Response Matrix Calculations,” PHYSOR 2012 – Advances in Reactor Physics, Knoxville, Tennessee, USA, April 15-20, (2012)
L.Zhu and B.Forget, “A Nonlinear Energy Acceleration Method,” Transactions of the American Nuclear Society, Hollywood, FL (2011)
J.Roberts and B.Forget, “Solving Eigenvalue Response Matrix Equations with Jacobian Free Newton Krylov Methods,” International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2011, Rio de Janeiro, Brazil, May 8-12 (2011).
B.Herman, E.Shwageraus, J.Leppanen and B.Forget, “Cross Section Generation Strategy for Advanced LWRs,” Proceedings of ICAPP, Nice, France, May 2-5 (2011)
J.Roberts and B.Forget, “Nonlinear Coarse Mesh Transport Using the Jacobian-Free Newton-Krylov Method,” Transactions of the American Nuclear Society, 102, 1, 533-535 (2010).
B.Forget and L.Zhu, “Mixed Energy Reactor Simulations using the Discrete Generalized Multigroup Method,” PHYSOR 2010, Pittsburgh, May (2010).
E.Sosnovsky, B.Forget and C.Newman, “Bond Graph based Coupled Reactor Simulations,” PHYSOR 2010, Pittsburgh, May (2010).

Nuclear data

Journal Publications

V.Sobes, L.Leal, G.Arbanas, B.Forget, “ Resonance Parameter Adjustment Based on Integral Experiments ”, Nuclear Science and Engineering, 347-355, 2016
Xingjie Peng, Pablo Ducru, Shichang Liu, Jingang Liang, Benoit Forget, Kord Smith, “ Converting point-wise nuclear cross sections to pole representation using regularized vector fitting ”, Computer Physics Communications, 224, 52-62, 2018
Shichang Liu, Xingjie Peng, Colin Josey, Jingang Liang, Benoit Forget, Kord Smith, Kan Wang, “ Generation of the windowed multipole resonance data using Vector Fitting technique ”, Research article, 112, 30-41, 2018
Pablo Ducru, Colin Josey, Karia Dibert, Vladimir Sobes, Kord Smith , “ Kernel reconstruction methods for Doppler broadening Temperature interpolation by linear combination of reference cross sections at optimally chosen temperatures ”, Journal of Computational Physics, 335, 535-557, 2017
J.Walsh, B.Forget, K.Smith, F.Brown, “ On-the-fly Doppler Broadening of Unresolved Resonance Region Cross Sections ”, Progress in Nuclear Energy, 101, 444-460, 2017
C.Josey, P.Ducru, B.Forget, K.Smith, “ Windowed Multipole for Cross Section Doppler Broadening ”, Journal of Computational Physics CASL Special Issue, 307, 715-727, 2016
P.Ducru, C.Josey, K.Dibert, V.Sobes, B.Forget, K.Smith, “Kernel Reconstruction methods for Doppler Broadening,” Journal of Computational Physics , 335, 535-557, 2017.
C.Josey, P.Ducru, B.Forget, K.Smith, “Windowed Multipole for Cross Section Doppler Broadening,” Journal of Computational Physics – CASL Special Issue, 307, 715-727, 2016.
V.Sobes, L.Leal, G.Arbanas, B.Forget, “Resonance Parameter Adjustment Based on Integral Experiments,” Nuclear Science and Engineering, 183 (3), 347-355, 2016.
C.Josey, B.Forget, K.Smith, “Windowed Multipole Sensitivity to Target Accuracy of the Optimization Procedure,” Journal of Nuclear Science and Technology, PHYSOR 2014 Special Issue, 52, Issue 7-8, 2015.
V.Sobes, L.C.Leal, K.Guber, B.Forget, S.Kopecky, P.Schillebeeckx, P.Siegler, “New Resolved Resonance Region Evaluation for Cu-63/65 for Nuclear Criticality Safety Program,” Nuclear Data Sheets, 118, 155-157, 2014.

Conference proceedings

J.Liang, X.Peng, S.Liu, C.Josey, B.Forget, K.Smith, “ Processing of a Comprehensive Windowed Multipole Library via Vector Fitting ”, PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, 2018
Jonathan A. Walsh, Benoit Forget, Kord S. Smith, Forrest B. Brown, “ Uncertainty in Fast Reactor-Relevant Critical Benchmark Simulations Due to Unresolved Resonance Structure ”, M&C 2017 Topical Meeting, 2017
Abdulla Alhajri, Vladimir Sobes, Chris Perfetti, Benoit Forget, “ Calculating Resonance Parameter Sensitivity Coefficients in SCALE ”, M&C 2017 Topical Meeting, 2017
M. Ellis, D. Gaston, B. Forget, and K. Smith, “ Continuous Temperature Representation in Coupled OpenMC/MOOSE Simulations ” PHYSOR 2016: Unifying Theory and Experiments in the 21st Century,177-192, 2016
V.Y.Tran, J.A.Walsh, B.Forget, “Treatments for Neutron Resonance Elastic Scattering Using the Multipole Formalism in Monte Carlo Codes,” Transactions of the American Nuclear Society, 115, 2016.
C.Haugen, B.Forget, K.Smith, “An Efficient Fourier Transform Method for Generation of Thermal Neutron Scattering Cross-Sections On-the-Fly,” ACEEES, San Diego, 2016.
P. Ducru, K. Dibert, C. Josey, B. Forget, V. Sobes, K. Smith, “Optimal Temperature Grid For Accurate Doppler Kernel Reconstruction,” Transactions of the American Nuclear Society, 115, 2016.
J. Walsh, B. Forget, K. Smith, and F. Brown, “On-The-Fly Doppler Broadening of Unresolved Resonance Region Cross Sections Via Probability Band Interpolation,” PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1-5, 2016.
P. Ducru, V. Sobes, B. Forget, and K. Smith, “On Methods for Conversion to Multipole Formalism,” PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1-5, 2016.
P.Ducru, V.Sobes, B.Forget, K.Smith, “Doppler Broadening by Linear Combination of Reference Temperature Cross Sections L2 Kernel Minimization Cross Section Temperature Interpolation Methods,” Transactions of the American Nuclear Society, 113, 656-660, 2015.
J.Walsh, B.Forget, K.Smith, B.Kiedrowski, F.Brown, “Direct, On-The-Fly Calculation of Unresolved Resonance Region Cross Sections in Monte Carlo Simulations,” M&C +SNA + MC 2015, Nashville, TN, April, 2015.
C.Josey, B.Forget, K.Smith, “Efficiency and Accuracy Evaluation of the Windowed Multipole Direct Doppler Broadening Method,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
V.Sobes, L.Leal, B.Forget, “Coupled Differential and Integral Data Analysis for Improved Uncertainty Quantification,” Transactions of the American Nuclear Society, 109, 857-860, 2013.
V.Sobes, L.Leal, K.Guber, B.Forget, S.Kopecky, P.Schillebeeckx, P.Siegler, “New Resolved Resonance Region Evaluation for Cu-63 and Cu-65 for Nuclear Criticality Safety Program,” International Conference on Nuclear Data for Science and Technology, ND2013, New York, 2013.
E.Paramonova, V.Sobes, B.Forget and G.Kohse, Radiative Capture Cross Section Measurement of Copper for EXFOR Database,” Transactions of the American Nuclear Society, 107, 360-361, 2012.
V.Sobes, B.Forget, L.Leal, K.Guber, “Preliminary Resolved Resonance Region Evaluation of Copper-63 from 0 to 300keV,” PHYSOR 2012 – Advances in Reactor Physics, Knoxville, Tennessee, USA, April 15-20, (2012)
V.Sobes, R.Macdonald, L.Leal, B.Forget, K.Guber and G.Kohse, “Thermal Total Cross Section Measurement for Cu-63 and Cu-65 at the MIT Reactor,” Transactions of the American Nuclear Society, 105, 557-558 (2011).
V.Sobes, L.Leal, D.Wiarda, D.Mueller, H.Derrien and B.Forget, “Processing and Testing New Pu-240 Resolved Resonance Evaluation,” Transactions of the American Nuclear Society, Hollywood, FL (2011)

Other

Journal Publications

M.Kostal, J.Milcak, V.Juricek, E.Losa, B.Forget, S.Harper, “ Study of Graphite Reactivity Worth on well-defined Core Assembled LR-0 Reactor ”, Annals of Nuclear Energy, 87, 601-611, 2016
M.Kostal, M.Veskrna, F.Cvachovec, B.Jansky, E.Novak, V.Rypar, J.Milcak, E.Losa, F.Mravec, Z.Matej, J.Rejchrt, B.Forget, S.Harper, “Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor,” Annals of Nuclear Energy, special issue, 83, 216-225, 2015.
M.Kostal, J.Milcak, V.Juricek, E.Losa, B.Forget, S.Harper, “Study of Graphite Reactivity Worth on well-defined Core Assembled LR-0 Reactor,” Annals of Nuclear Energy, 87, 601-611, 2016.
M. Massie and B.Forget, “Determining Optimal Neutron Spectra for Transmutation and Isotope Management,” Nucl. Tech., 182, 2, 207-223, 2013.
R.Petroski, B.Forget and C.Forsberg, “Evaluation of core compositions use in breed and burn reactors and limited-separations fuel cycles”, Annals of Nuc En., 55, 151-168, 2013.
R.Petroski, B.Forget and C.Forsberg, “Characterizing Limited Separations Fuel Cycles Using Breed-and-Burn Reactors”, Nuclear Technology, 180 (1), 28-45, 2012.
S. Kempf, B.Forget and L.W.Hu, “Kriging-Based Algorithm for Nuclear Reactor Neutronic Design Optimization,” Nuclear Engineering and Design, 247, 248-253, 2012.
R.Petroski, B.Forget and C.Forsberg, “Neutronic Characteristics of Linear-Assembly Breed-and-Burn Reactors”, Nuclear Engineering and Design, 250, 364-384, 2012.
B.Feng, E.Shwageraus, B.Forget, and M.S.Kazimi, "Light Water Breeding with Nitride Fuel," Progress in Nuclear Energy, 53 (7), 862-866 (2011).
V.Sobes, B.Forget and A.Kadak, “Individual pebble temperature peaking factor due to local pebble arrangement in a pebble bed reactor core” Nuclear Engineering and Design, 241 (1), 124-133 (2011)
R.Petroski, B.Forget and C.Forsberg, “Using the Neutron Excess Concept to Determine Starting Fuel Requirements for Minimum-Burnup Breed-and-Burn Reactors”, Nuclear Technology, 175 (2), 388-400 (2011).
N.Stauff, M.J.Driscoll, B.Forget, P.Hejzlar, “Resolution of Proliferation Issues for a Sodium Fast Reactor Blanket,” Nucl. Tech., 170 (2010).

Conference proceedings

Jingang Liang, Shikhar Kumar, Benoit Forget, Kord Smith, “ Quantifying Uncertainty in the BEAVRS Benchmark ”, M&C 2017 Topical Meeting, 2017
S. Kumar, J.Liang, B.Forget, K. Smith, “Quantifying Transient Uncertainty in the BEAVRS Benchmark Using Time Series Analysis Methods,” Transactions of the American Nuclear Society, 115, 2016.
J.Richard, B.Forget, C.Forsberg, K.Smith, “Neutronic Comparison of Liquid Salt Primary Coolants and Novel Assembly Design for a Fluoride Salt Cooled High-Temperature Test Reactor,” Transactions of the American Nuclear Society, 111, 1076-1081, 2014.
D.J.Kelly, B.N.Aviles, P.K.Romano, B.R.Herman, N.E.Horelik, B.Forget “Analysis of Select BEAVRS PWR Benchmark Cycle 1 Results using MC21 and OpenMC,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
B.Forget, K.S.Smith, “Past, Present and Future of MIT Reactor Physics,” PHYSOR 2014 – The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, 2014.
J.Richard, B.Forget and C.Forsberg, “Core design evolution of a fluoride salt cooled high-temperature test reactor,” Proceedings of ICAPP 2014, Charlotte, NC, April 6-9, 2014.
J.Richard, D.Wang, G.Yoder, J.Carbajo, D.Williams, B.Forget and C.Forsberg, “Implementation of Liquid Salt Working Fluids into TRACE,” Proceedings of ICAPP 2014, Charlotte, NC, April 6-9, 2014.
N.Horelik, B.Herman, B.Forget, K.Smith, "MIT BEAVRS: Benchmark for Evaluation and Validation of Reactor Simulations", International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013, Sun Valley, ID, May 5-9, 2013.
K.Smith, B.Forget, "Challenges in the Development of High-Fidelity LWR Core Neutronics Tools," International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013, Sun Valley, ID, May 5-9, 2013.
J.Richard, M.Short, S.Don, B.Forget, R.R.Romatoski, L.W.Hu, C.Forsberg, “Preliminary Design of a Prismatic Core Fluoride-Salt Cooled High-Temperature Test Reactor,” International Congress on Advances in Nuclear Power Plants, ICAPP 2013, Jeju Island, Korea, 2013.
M. Massie, C.Forsberg, B.Forget, L.W. Hu, “Preliminary Requirements for a Fluoride Salt-Cooled High Temperature Test Reactor,” ICAPP 2012, June 2012.
K.Y. Chiang, L.W. Hu and B.Forget, “Thermal Hydraulic Limits Analysis using Statistical Propagation of Parametric Uncertainties,” ICAPP 2012, June 2012.
M. Reed, R. Parker, B. Forget. “A Fission-Fusion Hybrid Reactor in L-Mode Tokamak Configuration with Natural Uranium”. Fusion for Neutrons and Subcritical Nuclear Fission (FUNFI). American Institute of Physics (AIP) Conference Proceedings 1442, 224-231 (2012).
B.Feng, E.Shwageraus, B.Forget, and M.S.Kazimi, "Light Water Breeding with Nitride Fuel," INES-3 Symposium, Tokyo, Japan, Oct. 31-Nov. 3 (2010).
M.Massie and B.Forget, “Quantitative Optimization of Target Assembly Material Compositions for Isotope Management,” Transactions of the American Nuclear Society, 103, 1, 746-747 (2010).
R.Petroski, B.Forget and C.Forsberg, “Definition and Applications of the Neutron Excess Concept,” Transactions of the American Nuclear Society, 103, 1, 88-89 (2010).
T.H.Newton, H.Horelik, P.Romano, B.Forget, E.Pilat, E.H.Wilson, B.Dionne, A.Bergeron and J.Stevens, “LEU Conversion Activities at the MIT Research Reactor: Use of Neutronic Models for Safety Analsyses,” RERTR 2010 – 32nd International Meeting on Reduced Enrichement for Research and Test Reactors, Lisbon, Portugal, October 10-14 (2010).
R.Petroski, B.Forget and C.Forsberg, “Neutronic Evaluation of Breed-and -Burn Reactor Fuel Types Using an Infinite-Medium Depletion Approximation,” PHYSOR 2010, Pittsburgh, May (2010).
T.H. Newton, Jr., L-W Hu, G. E. Kohse, E. E. Pilat, B. Forget, P. K. Romano, Y-C Ko, S. Wong, Y. Wang, B.Dionne, J. Thomas and A. Olson, “Completion of Feasibility Studies on using LEU fuel in the MIT Reactor,” International Meeting on Reduced Enrichment for Research and Test Reactors, RERTR 2009, Beijing (2009).
N.Stauff, B.Forget, M.Driscoll, “Resolution of proliferation issues for a SFR blanket with a specific application,” GLOBAL 2009 - The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives, Paris, France, September 6th-11th (2009).
P.Romano, B.Forget and T.Newton, “Development of a Graphical User Interface for In-core Fuel Management using MCODE,” Advances in Nuclear Fuel Management IV, Hilton Head Island, South Carolina, USA, April 12-15 (2009)
T.Newton, P.Romano, B.Forget, “REBUS and MCODE Burnup Modeling of the MITR for Conversion Studies,” RERTR International Meeting (2008)
P.Romano, B.Forget and T.Newton, “Extending MCODE Capabilities for Innovative Design Studies at the MITR,” ANS Winter Meeting, Reno, NV (2008).