.. _publications: ============ Publications ============ Citing OpenMOC ============== Please cite OpenMOC in your publications if it helps your research: .. code-block:: latex @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. .. _Google Scholar: https://scholar.google.com/scholar?cites=3139736083643679686&as_sdt=40000005&sciodt=0,22&hl=en .. _CRPG: https://crpg.mit.edu/publications 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) - G. 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) - 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) - 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).