Publications

Overviews

• Paul K. Romano, Nicholas E. Horelik, Bryan R. Herman, Adam G. Nelson, Benoit Forget, and Kord Smith, “OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development,” Ann. Nucl. Energy, 82, 90–97 (2015).
• Paul K. Romano, Bryan R. Herman, Nicholas E. Horelik, Benoit Forget, Kord Smith, and Andrew R. Siegel, “Progress and Status of the OpenMC Monte Carlo Code,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, May 5–9 (2013).
• Paul K. Romano and Benoit Forget, “The OpenMC Monte Carlo Particle Transport Code,” Ann. Nucl. Energy, 51, 274–281 (2013).

Benchmarking

• Travis J. Labossiere-Hickman and Benoit Forget, “Selected VERA Core Physics Benchmarks in OpenMC,” Trans. Am. Nucl. Soc., 117, 1520-1523 (2017).
• Khurrum S. Chaudri and Sikander M. Mirza, “Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark,” Prog. Nucl. Energy, 81, 43-52 (2015).
• Daniel J. Kelly, Brian N. Aviles, Paul K. Romano, Bryan R. Herman, Nicholas E. Horelik, and Benoit Forget, “Analysis of select BEAVRS PWR benchmark cycle 1 results using MC21 and OpenMC,” Proc. PHYSOR, Kyoto, Japan, Sep. 28–Oct. 3 (2014).
• Bryan R. Herman, Benoit Forget, Kord Smith, Paul K. Romano, Thomas M. Sutton, Daniel J. Kelly, III, and Brian N. Aviles, “Analysis of tally correlations in large light water reactors,” Proc. PHYSOR, Kyoto, Japan, Sep. 28–Oct. 3 (2014).
• Nicholas Horelik, Bryan Herman, Benoit Forget, and Kord Smith, “Benchmark for Evaluation and Validation of Reactor Simulations,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, May 5–9 (2013).
• Jonathan A. Walsh, Benoit Forget, and Kord S. Smith, “Validation of OpenMC Reactor Physics Simulations with the B&W 1810 Series Benchmarks,” Trans. Am. Nucl. Soc., 109, 1301–1304 (2013).

Coupling and Multi-physics

• Miriam A. Kreher, Benoit Forget, and Kord Smith, “Single-Batch Monte Carlo Multiphysics Coupling,” Proc. M&C, 1789-1797, Portland, Oregon, Aug. 25-29 (2019).
• Ze-Long Zhao, Yongwei Yang, and Shuang Hong, “Application of FLUKA and OpenMC in coupled physics calculation of target and subcritical reactor for ADS,” Nucl. Sci. Tech., 30: 10 (2019).
• April Novak, Paul Romano, Brycen Wendt, Ron Rahaman, Elia Merzari, Leslie Kerby, Cody Permann, Richard Martineau, and Rachel N. Slaybaugh, “Preliminary Coupling of OpenMC and Nek5000 within the MOOSE Framework,” Proc. PHYSOR, Cancun, Mexico, Apr. 22-26 (2018).
• Jun Chen, Liangzhi Cao, Chuanqi Zhao, and Zhouyu Liu, “Development of Subchannel Code SUBSC for high-fidelity multi-physics coupling application”, Energy Procedia, 127, 264-274 (2017).
• Tianliang Hu, Liangzhu Cao, Hongchun Wu, Xianan Du, and Mingtao He, “Coupled neutrons and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY,” Ann. Nucl. Energy, 109, 260-276 (2017).
• Matthew Ellis, Derek Gaston, Benoit Forget, and 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,” Nucl. Sci. Eng., 185, 184-193 (2017).
• Matthew Ellis, Benoit Forget, Kord Smith, and Derek Gaston, “Continuous Temperature Representation in Coupled OpenMC/MOOSE Simulations,” Proc. PHYSOR 2016, Sun Valley, Idaho, May 1-5, 2016.
• Antonios G. Mylonakis, Melpomeni Varvayanni, and Nicolas Catsaros, “Investigating a Matrix-free, Newton-based, Neutron-Monte Carlo/Thermal-Hydraulic Coupling Scheme”, Proc. Int. Conf. Nuclear Energy for New Europe, Portoroz, Slovenia, Sep .14-17 (2015).
• Matt Ellis, Benoit Forget, Kord Smith, and Derek Gaston, “Preliminary coupling of the Monte Carlo code OpenMC and the Multiphysics Object-Oriented Simulation Environment (MOOSE) for analyzing Doppler feedback in Monte Carlo simulations,” Proc. Joint Int. Conf. M&C+SNA+MC, Nashville, Tennessee, Apr. 19–23 (2015).
• Bryan R. Herman, Benoit Forget, and Kord Smith, “Progress toward Monte Carlo-thermal hydraulic coupling using low-order nonlinear diffusion acceleration methods,” Ann. Nucl. Energy, 84, 63-72 (2015).
• Bryan R. Herman, Benoit Forget, and Kord Smith, “Utilizing CMFD in OpenMC to Estimate Dominance Ratio and Adjoint,” Trans. Am. Nucl. Soc., 109, 1389-1392 (2013).

Geometry and Visualization

• Sterling Harper, Paul Romano, Benoit Forget, and Kord Smith, “Efficient dynamic threadsafe neighbor lists for Monte Carlo ray tracing,” Proc. M&C, 918-926, Portland, Oregon, Aug. 25-29 (2019).
• Jin-Yang Li, Long Gu, Hu-Shan Xu, Nadezha Korepanova, Rui Yu, Yan-Lei Zhu, and Chang-Ping Qin, “CAD modeling study on FLUKA and OpenMC for accelerator driven system simulation”, Ann. Nucl. Energy, 114, 329-341 (2018).
• Logan Abel, William Boyd, Benoit Forget, and Kord Smith, “Interactive Visualization of Multi-Group Cross Sections on High-Fidelity Spatial Meshes,” Trans. Am. Nucl. Soc., 114, 391-394 (2016).
• Derek M. Lax, “Memory efficient indexing algorithm for physical properties in OpenMC,” S. M. Thesis, Massachusetts Institute of Technology (2015).
• Derek Lax, William Boyd, Nicholas Horelik, Benoit Forget, and Kord Smith, “A memory efficient algorithm for classifying unique regions in constructive solid geometries,” Proc. PHYSOR, Kyoto, Japan, Sep. 28–Oct. 3 (2014).

Miscellaneous

• Shikhar Kumar, Benoit Forget, and Kord Smith, “Analysis of fission source convergence for a 3-D SMR core using functional expansion tallies,” Proc. M&C, 937-947, Portland, Oregon, Aug. 25-29 (2019).
• Faisal Qayyum, Muhammad R. Ali, Awais Zahur, and R. Khan, “Improvements in methodology to determine feedback reactivity coefficients,” Nucl. Sci. Tech., 30: 63 (2019).
• M. Sajjad, Muhammad Rizwan Ali, M. Naveed Ashraf, Rustam Khan, Tasneem Fatima, “KANUPP Reactor Core Model and its Validation,” International Conference on Power Generation Systems and Renewable Energy Technologies, Islamabad, Pakistan, Sep. 10-12 (2018).
• Muhammad Waqas Tariq, Muhammad Sohail, and Sikander Majid Mirza, “Calculation of Neutronic Parameters using OpenMC for Potential Dispersed Fuels of MNSR,” International Conference on Power Generation Systems and Renewable Energy Technologies, Islamabad, Pakistan, Sep. 10-12 (2018).
• Amanda L. Lund and Paul K. Romano, “Implementation and Validation of Photon Transport in OpenMC”, Argonne National Laboratory, Technical Report ANL/MCS-TM-381 (2018).
• Bruno Merk, Dzianis Litskevich, R. Gregg, and A. R. Mount, “Demand driven salt clean-up in a molten salt fast reactor – Defining a priority list”, PLOS One, 13, e0192020 (2018).
• Adam G. Nelson, Samuel Shaner, William Boyd, and Paul K. Romano, “Incorporation of a Multigroup Transport Capability in the OpenMC Monte Carlo Particle Transport Code,” Trans. Am. Nucl. Soc., 117, 679-681 (2017).
• Youqi Zheng, Yunlong Xiao, and Hongchun Wu, “Application of the virtual density theory in fast reactor analysis based on the neutron transport calculation,” Nucl. Eng. Des., 320, 200-206 (2017).
• Amanda L. Lund, Paul K. Romano, and Andrew R. Siegel, “Accelerating Source Convergence in Monte Carlo Criticality Calculations Using a Particle Ramp-Up Technique,” Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear Science and Engineering, Jeju, Korea, Apr. 16-20, 2017.
• Antonios G. Mylonakis, M. Varvayanni, D.G.E. Grigoriadis, and N. Catsaros, “Developing and investigating a pure Monte-Carlo module for transient neutron transport analysis,” Ann. Nucl. Energy, 104, 103-112 (2017).
• Timothy P. Burke, Brian C. Kiedrowski, William R. Martin, and Forrest B. Brown, “GPU Acceleration of Kernel Density Estimators in Monte Carlo Neutron Transport Simulations,” Trans. Am. Nucl. Soc., 115, 531-534 (2016).
• Timothy P. Burke, Brian C. Kiedrowski, and William R. Martin, “Cylindrical Kernel Density Estimators for Monte Carlo Neutron Transport Reactor Physics Problems,” Trans. Am. Nucl. Soc., 115, 563-566 (2016).
• Yunzhao Li, Qingming He, Liangzhi Cao, Hongchun Wu, and Tiejun Zu, “Resonance Elastic Scattering and Interference Effects Treatments in Subgroup Method,” Nucl. Eng. Tech., 48, 339-350 (2016).
• William Boyd, Sterling Harper, and Paul K. Romano, “Equipping OpenMC for the big data era,” Proc. PHYSOR, Sun Valley, Idaho, May 1-5, 2016.
• Michal Kostal, Vojtech Rypar, Jan Milcak, Vlastimil Juricek, Evzen Losa, Benoit Forget, and Sterling Harper, “Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor,” Ann. Nucl. Energy, 87, 601-611 (2016).
• Qicang Shen, William Boyd, Benoit Forget, and Kord Smith, “Tally precision triggers for the OpenMC Monte Carlo code,” Trans. Am. Nucl. Soc., 112, 637-640 (2015).
• Kyungkwan Noh and Deokjung Lee, “Whole Core Analysis using OpenMC Monte Carlo Code,” Trans. Kor. Nucl. Soc. Autumn Meeting, Gyeongju, Korea, Oct. 24-25, 2013.
• Timothy P. Burke, Brian C. Kiedrowski, and William R. Martin, “Flux and Reaction Rate Kernel Density Estimators in OpenMC,” Trans. Am. Nucl. Soc., 109, 683-686 (2013).

Multigroup Cross Section Generation

• William Boyd, Adam Nelson, Paul K. Romano, Samuel Shaner, Benoit Forget, and Kord Smith, “Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code,” Nucl. Technol. (2019).
• William Boyd, Benoit Forget, and Kord Smith, “A single-step framework to generate spatially self-shielded multi-group cross sections from Monte Carlo transport simulations,” Ann. Nucl. Energy, 125, 261-271 (2019).
• Kun Zhuang, Xiaobin Tang, and Liangzhi Cao, “Development and verification of a model for generation of MSFR few-group homogenized cross-sections based on a Monte Carlo code OpenMC,” Ann. Nucl. Energy, 124, 187-197 (2019).
• Changho Lee and Yeon Sang Jung, “Verification of the Cross Section Library Generated Using OpenMC and MC²-3 for PROTEUS,” Proc. PHYSOR, Cancun, Mexico, Apr. 22-26 (2018).
• Zhaoyuan Liu, Kord Smith, Benoit Forget, and Javier Ortensi, “Cumulative migration method for computing rigorous diffusion coefficients and transport cross sections from Monte Carlo,” Ann. Nucl. Energy, 112, 507-516 (2018).
• Gang Yang, Tongkyu Park, and Won Sik Yang, “Effects of Fuel Salt Velocity Field on Neutronics Performances in Molten Salt Reactors with Open Flow Channels,” Trans. Am. Nucl. Soc., 117, 1339-1342 (2017).
• William Boyd, Nathan Gibson, Benoit Forget, and Kord Smith, “An analysis of condensation errors in multi-group cross section generation for fine-mesh neutron transport calculations,” Ann. Nucl. Energy, 112, 267-276 (2018).
• Hong Shuang, Yang Yongwei, Zhang Lu, and Gao Yucui, “Fabrication and validation of multigroup cross section library based on the OpenMC code,” Nucl. Techniques 40 (4), 040504 (2017). (in Mandarin)
• Nicholas E. Stauff, Changho Lee, Paul K. Romano, and Taek K. Kim, “Verification of Mixed Stochastic/Deterministic Approach for Fast and Thermal Reactor Analysis,” Proc. ICAPP, Fukui and Kyoto, Japan, Apr. 24-28, 2017.
• Zhauyuan Liu, Kord Smith, and Benoit Forget, “Progress of Cumulative Migration Method for Computing Diffusion Coefficients with OpenMC,” Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear Science and Engineering, Jeju, Korea, Apr. 16-20, 2017.
• Geoffrey Gunow, Samuel Shaner, William Boyd, Benoit Forget, and Kord Smith, “Accuracy and Performance of 3D MOC for Full-Core PWR Problems,” Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear Science and Engineering, Jeju, Korea, Apr. 16-20, 2017.
• Tianliang Hu, Liangzhi Cao, Hongchun Wu, and Kun Zhuang, “A coupled neutronics and thermal-hydraulic modeling approach to the steady-state and dynamic behavior of MSRs,” Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear Science and Engineering, Jeju, Korea, Apr. 16-20, 2017.
• William R. D. Boyd, “Reactor Agnostic Multi-Group Cross Section Generation for Fine-Mesh Deterministic Neutron Transport Simulations,” Ph.D. Thesis, Massachusetts Institute of Technology (2017).
• Zhaoyuan Liu, Kord Smith, and Benoit Forget, “A Cumulative Migration Method for Computing Rigorous Transport Cross Sections and Diffusion Coefficients for LWR Lattices with Monte Carlo,” Proc. PHYSOR, Sun Valley, Idaho, May 1-5, 2016.
• Adam G. Nelson and William R. Martin, “Improved Monte Carlo tallying of multi-group scattering moments using the NDPP code,” Trans. Am. Nucl. Soc., 113, 645-648 (2015)
• Adam G. Nelson and William R. Martin, “Improved Monte Carlo tallying of multi-group scattering moment matrices,” Trans. Am. Nucl. Soc., 110, 217-220 (2014).
• Adam G. Nelson and William R. Martin, “Improved Convergence of Monte Carlo Generated Multi-Group Scattering Moments,” Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, May 5–9 (2013).

Doppler Broadening

• Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown, “On-the-fly Doppler broadening of unresolved resonance region cross sections,” Prog. Nucl. Energy, 101, 444-460 (2017).
• Colin Josey, Pablo Ducru, Benoit Forget, and Kord Smith, “Windowed multipole for cross section Doppler broadening,” J. Comput. Phys., 307, 715-727 (2016).
• Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown, “On-the-fly Doppler Broadening of Unresolved Resonance Region Cross Sections via Probability Band Interpolation,” Proc. PHYSOR, Sun Valley, Idaho, May 1-5, 2016.
• Jonathan A. Walsh, Benoit Forget, Kord S. Smith, Brian C. Kiedrowski, and Forrest B. Brown, “Direct, on-the-fly calculation of unresolved resonance region cross sections in Monte Carlo simulations,” Proc. Joint Int. Conf. M&C+SNA+MC, Nashville, Tennessee, Apr. 19–23 (2015).
• Colin Josey, Benoit Forget, and Kord Smith, “Windowed multipole sensitivity to target accuracy of the optimization procedure,” J. Nucl. Sci. Technol., 52, 987-992 (2015).
• Paul K. Romano and Timothy H. Trumbull, “Comparison of algorithms for Doppler broadening pointwise tabulated cross sections,” Ann. Nucl. Energy, 75, 358–364 (2015).
• Tuomas Viitanen, Jaakko Leppanen, and Benoit Forget, “Target motion sampling temperature treatment technique with track-length esimators in OpenMC – Preliminary results,” Proc. PHYSOR, Kyoto, Japan, Sep. 28–Oct. 3 (2014).
• Benoit Forget, Sheng Xu, and Kord Smith, “Direct Doppler broadening in Monte Carlo simulations using the multipole representation,” Ann. Nucl. Energy, 64, 78–85 (2014).

Nuclear Data

• Jonathan A. Walsh, “Comparison of Unresolved Resonance Region Cross Section Formalisms in Transport Simulations,” Trans. Am. Nucl. Soc., 117, 749-752 (2017).
• Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown, “Uncertainty in Fast Reactor-Relevant Critical Benchmark Simulations Due to Unresolved Resonance Structure,” Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear Science and Engineering, Jeju, Korea, Apr. 16-20, 2017.
• Vivian Y. Tran, Jonathan A. Walsh, and Benoit Forget, “Treatments for Neutron Resonance Elastic Scattering Using the Multipole Formalism in Monte Carlo Codes,” Trans. Am. Nucl. Soc., 115, 1133-1137 (2016).
• Paul K. Romano and Sterling M. Harper, “Nuclear data processing capabilities in OpenMC”, Proc. Nuclear Data, Sep. 11-16, 2016.
• Jonathan A. Walsh, Benoit Froget, Kord S. Smith, and Forrest B. Brown, “Neutron Cross Section Processing Methods for Improved Integral Benchmarking of Unresolved Resonance Region Evaluations,” Eur. Phys. J. Web Conf. 111, 06001 (2016).
• Jonathan A. Walsh, Paul K. Romano, Benoit Forget, and Kord S. Smith, “Optimizations of the energy grid search algorithm in continuous-energy Monte Carlo particle transport codes”, Comput. Phys. Commun., 196, 134-142 (2015).
• Amanda L. Lund, Andrew R. Siegel, Benoit Forget, Colin Josey, and Paul K. Romano, “Using fractional cascading to accelerate cross section lookups in Monte Carlo particle transport calculations,” Proc. Joint Int. Conf. M&C+SNA+MC, Nashville, Tennessee, Apr. 19–23 (2015).
• Ronald O. Rahaman, Andrew R. Siegel, and Paul K. Romano, “Monte Carlo performance analysis for varying cross section parameter regimes,” Proc. Joint Int. Conf. M&C+SNA+MC, Nashville, Tennessee, Apr. 19–23 (2015).
• Jonathan A. Walsh, Benoit Forget, and Kord S. Smith, “Accelerated sampling of the free gas resonance elastic scattering kernel,” Ann. Nucl. Energy, 69, 116–124 (2014).

Parallelism

• Paul K. Romano and Andrew R. Siegel, “Limits on the efficiency of event-based algorithms for Monte Carlo neutron transport,” Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear Science and Engineering, Jeju, Korea, Apr. 16-20, 2017.
• Paul K. Romano, John R. Tramm, and Andrew R. Siegel, “Efficacy of hardware threading for Monte Carlo particle transport calculations on multi- and many-core systems,” PHYSOR 2016, Sun Valley, Idaho, May 1-5, 2016.
• David Ozog, Allen D. Malony, and Andrew R. Siegel, “A performance analysis of SIMD algorithms for Monte Carlo simulations of nuclear reactor cores,” Proc. IEEE Int. Parallel and Distributed Processing Symposium, Hyderabad, India, May 25–29 (2015).
• David Ozog, Allen D. Malony, and Andrew Siegel, “Full-core PWR transport simulations on Xeon Phi clusters,” Proc. Joint Int. Conf. M&C+SNA+MC, Nashville, Tennessee, Apr. 19–23 (2015).
• Paul K. Romano, Andrew R. Siegel, and Ronald O. Rahaman, “Influence of the memory subsystem on Monte Carlo code performance,” Proc. Joint Int. Conf. M&C+SNA+MC, Nashville, Tennessee, Apr. 19–23 (2015).
• Hajime Fujita, Nan Dun, Aiman Fang, Zachary A. Rubinstein, Ziming Zheng, Kamil Iskra, Jeff Hammonds, Anshu Dubey, Pavan Balaji, and Andrew A. Chien, “Using Global View Resilience (GVR) to add Resilience to Exascale Applications,” Proc. Supercomputing, New Orleans, Louisiana, Nov. 16–21, 2014.
• Nicholas Horelik, Benoit Forget, Kord Smith, and Andrew Siegel, “Domain decomposition and terabyte tallies with the OpenMC Monte Carlo neutron transport code,” Proc. PHYSOR, Kyoto Japan, Sep. 28–Oct. 3 (2014).
• John R. Tramm, Andrew R. Siegel, Tanzima Islam, and Martin Schulz, “XSBench – the development and verification of a performance abstraction for Monte Carlo reactor analysis,” Proc. PHYSOR, Kyoto, Japan, Sep 28–Oct. 3, 2014.
• Nicholas Horelik, Andrew Siegel, Benoit Forget, and Kord Smith, “Monte Carlo domain decomposition for robust nuclear reactor analysis,” Parallel Comput., 40, 646–660 (2014).
• Andrew Siegel, Kord Smith, Kyle Felker, Paul Romano, Benoit Forget, and Peter Beckman, “Improved cache performance in Monte Carlo transport calculations using energy banding,” Comput. Phys. Commun., 185 (4), 1195–1199 (2014).
• Paul K. Romano, Benoit Forget, Kord Smith, and Andrew Siegel, “On the use of tally servers in Monte Carlo simulations of light-water reactors,” Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, Paris, France, Oct. 27–31 (2013).
• Kyle G. Felker, Andrew R. Siegel, Kord S. Smith, Paul K. Romano, and Benoit Forget, “The energy band memory server algorithm for parallel Monte Carlo calculations,” Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, Paris, France, Oct. 27–31 (2013).
• John R. Tramm and Andrew R. Siegel, “Memory Bottlenecks and Memory Contention in Multi-Core Monte Carlo Transport Codes,” Proc. Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, Paris, France, Oct. 27–31 (2013).
• Andrew R. Siegel, Kord Smith, Paul K. Romano, Benoit Forget, and Kyle Felker, “Multi-core performance studies of a Monte Carlo neutron transport code,” Int. J. High Perform. Comput. Appl., 28 (1), 87–96 (2014).
• Paul K. Romano, Andrew R. Siegel, Benoit Forget, and Kord Smith, “Data decomposition of Monte Carlo particle transport simulations via tally servers,” J. Comput. Phys., 252, 20–36 (2013).
• Andrew R. Siegel, Kord Smith, Paul K. Romano, Benoit Forget, and Kyle Felker, “The effect of load imbalances on the performance of Monte Carlo codes in LWR analysis,” J. Comput. Phys., 235, 901–911 (2013).
• Paul K. Romano and Benoit Forget, “Reducing Parallel Communication in Monte Carlo Simulations via Batch Statistics,” Trans. Am. Nucl. Soc., 107, 519–522 (2012).
• Paul K. Romano and Benoit Forget, “Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations,” Nucl. Sci. Eng., 170, 125–135 (2012).

Depletion

• Jose L. Salcedo-Perez, Benoit Forget, Kord Smith, and Paul Romano, “Hybrid tallies to improve performance in depletion Monte Carlo simulations,” Proc. M&C, 927-936, Portland, Oregon, Aug. 25-29 (2019).
• Zhao-Qing Liu, Ze-Long Zhao, Yong-Wei Yang, Yu-Cui Gao, Hai-Yan Meng, and Qing-Yu Gao, “Development and validation of depletion code system IMPC-Burnup for ADS,” Nucl. Sci. Tech., 30: 44 (2019).
• Colin Josey, Benoit Forget, and Kord Smith, “High order methods for the integration of the Bateman equations and other problems of the form of y’ = F(y,t)y,” J. Comput. Phys., 350, 296-313 (2017).
• Matthew S. Ellis, Colin Josey, Benoit Forget, and Kord Smith, “Spatially Continuous Depletion Algorithm for Monte Carlo Simulations,” Trans. Am. Nucl. Soc., 115, 1221-1224 (2016).
• Anas Gul, K. S. Chaudri, R. Khan, and M. Azeen, “Development and verification of LOOP: A Linkage of ORIGEN2.2 and OpenMC,” Ann. Nucl. Energy, 99, 321–327 (2017).
• Kai Huang, Hongchun Wu, Yunzhao Li, and Liangzhi Cao, “Generalized depletion chain simplification based of significance analysis,” Proc. PHYSOR, Sun Valley, Idaho, May 1-5, 2016.

Sensitivity Analysis

• Abdulla Alhajri and Benoit Forget, “Eigenvalue Sensitivity in Monte Carlo Simulations to Nuclear Data Parameters using the Multipole Formalism,” Proc. M&C, 1895-1906, Portland, Oregon, Aug. 25-29 (2019).
• Xingjie Peng, Jingang Liang, Benoit Forget, and Kord Smith, “Calculation of adjoint-weighted reactor kinetics parameters in OpenMC”, Ann. Nucl. Energy, 128, 231-235 (2019).
• Zeyun Wu, Jingang Liang, Xingjie Peng, and Hany S. Abdel-Khalik, “GPT-Free Sensitivity Analysis for Monte Carlo Models”, Nucl. Technol. (2019).
• Xingjie Peng, Jingang Liang, Abdulla Alhajri, Benoit Forget, and Kord Smith, “Development of continuous-energy sensitivity analysis capability in OpenMC”, Ann. Nucl. Energy, 110, 362-383 (2017).