Publications¶
Citing OpenMOC¶
Please cite OpenMOC in your publications if it helps your research:
@article{openmoc2014,
author = {Boyd, William and Shaner, Samuel and Li, Lulu and Forget, Benoit and Smith, Kord},
journal = {Annals of Nuclear Energy},
title = {The OpenMOC Method of Characteristics Neutral Particle Transport Code},
volume = {68},
pages = {43--52},
year = {2014}
}
Citations are tracked automatically by Google Scholar. A more comprehensive list of publications is available on the CRPG website.
Journals¶
- Zhaoyuan Liu, Kord Smith and Benoit Forget, “Calculation Method for Multi-group Migration Area in Deterministic Simulation Methods”, To be published (2019)
- Zhaoyuan Liu, Guillaume Giudicelli, Kord Smith and Benoit Forget, “Transport Correction using Cumulative Migration Method by Conserving Migration Area”, To be published (2019)
- Geoffrey Gunow, Benoit Forget, Kord Smith, “Full Core 3D Simulation of the BEAVRS Benchmark with OpenMOC”, Annals of Nuclear Energy, Volume 134, December 2019, Pages 299-304
- 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)
- William Boyd, Andrew Siegel, Benoit Forget and Kord Smith, “Parallel Performance Results for the OpenMOC Neutron Transport Code on Multi-Core Platforms.” Int’l Journ. of High Perf. Comp. Appl., 30 (2016).
- Matthew Everson and Benoit Forget, “The Source Equivalence Acceleration Method.” Annals of Nuclear Energy, 76 (2015): 177–129.
- 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)
- William Boyd, Samuel Shaner, Lulu Li, Benoit Forget, and Kord Smith, “The OpenMOC Method of Characteristics Neutral Particle Transport Code.” Annals of Nuclear Energy, 68 (2014): 43–52.
Conference Papers¶
- 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)
- Gunow, S. Shaner, W. Boyd, B. Forget, K. Smith, “Accuracy and Performance of 3D MOC for Full-Core PWR Problems”, M&C 2017 Topical Meeting, (2017)
- 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)
- 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)
- William Boyd, Samuel Shaner, Benoit Forget and Kord Smith, “Program Optimization and Improved Workflow Synthesis for the OpenMOC Neutron Transport Code.” Trans. of the Amer. Nucl. Soc., ANS Winter Meeting, Washington, D.C., USA, November (2015).
- William Boyd, Kazutomo Yoshii and Andrew Siegel, “Energy Efficiency of High-Performance Computing Platforms for Neutron Transport Calculations.” Trans. of the Amer. Nucl. Soc., ANS Summer Meeting, San Antonio, TX, USA June (2015).
- William Boyd, Kord Smith, Benoit Forget, and Andrew Siegel, “Parallel Performance Results for the OpenMOC Method of Characteristics Code on Multi-Core Platforms.” Proceedings of PHYSOR, Kyoto, Japan (2014).
- Lulu Li, Kord Smith, and Benoit Forget, “Low Order Nonlinear Transport Acceleration Scheme for the Method of Characteristics.” Proceedings of PHYSOR, Kyoto, Japan (2014).
- Samuel Shaner, Kord Smith, and Benoit Forget, “Sensitivity Analysis and Performance of the Adiabatic, Theta, and Multigrid Amplitude Function Kinetics Methods in 2D MOC Neutron Transport.” Proceedings of PHYSOR, Kyoto, Japan (2014).
- Stephanie Pavlick, Davis Tran, Jasmeet Arora, and William Boyd, “Lattice Benchmark Verification of OpenMOC.” Proc. Amer. Nucl. Soc. Student Conf., University Park, PA, USA (2014).
- William Boyd, Kord Smith, and Benoit Forget, “A Massively Parallel Method of Characteristic Neutral Particle Transport Code for GPUs.” Proc. Int’l Conf. Math. and Comp. Methods Appl. to Nucl. Sci. and Eng., Sun Valley, ID, USA (2013). Selected for Best Overall Conference Paper.
Theses¶
- Geoff Gunow, “Full Core 3D Neutron Transport Simulation Using the Method of Characteristics with Linear Sources”, PhD Thesis, Massachusetts Institute of Technology (2018).
- William R. D. Boyd III, “Reactor agnostic multi-group cross section generation for fine-mesh deterministic neutron transport simulations” PhD Thesis, Massachusetts Institute of Technology (2017).
- Samuel Shaner, “Transient Method of Characteristics via the Adiabatic, Theta, and Multigrid Amplitude Function Methods.” M.S. Thesis, Massachusetts Institute of Technology (2014).
- William R. D. Boyd III, “Massively Parallel Algorithms for Method of Characteristics Neutral Particle Transport on Shared Memory Computer Architectures.” M.S. Thesis, Massachusetts Institute of Technology (2014).
- Matthew Everson, “Advanced Application of the Discrete Generalized Multigroup Method and Recondensation to Reactor Analysis.” PhD Thesis, Massachusetts Institute of Technology (2014).
- Lulu Li, “A Low Order Acceleration Scheme for Solving the Neutron Transport Equation.” M.S. Thesis, Massachusetts Institute of Technology (2013).