**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).