References
- J. Askew, A Characteristics Formulation of the Neutron Transport Equation in Complicated Geometries, AEEW-M 1108, The United Kingdom Atomic Energy Authority, 1972.
- K. Smith, J. Rhodes, Full-core, 2-D, LWR Core Calculations with CASMO-4E, PHYSOR 2002, Seoul, Korea, 2002.
- W. Boyd, S. Shaner, L. Li, et al., The OpenMOC method of characteristics neutral particle transport code, Ann. Nucl. Energy 68 (2014) 43-52. https://doi.org/10.1016/j.anucene.2013.12.012
- G. Gunow, S. Shaner, W. Boyd, Accuracy and performance of 3D MOC for fullcore PWR problems, in: M&C 2017 - International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, 2017.
- K. Smith, Nodal method storage reduction by nonlinear iteration, Trans. Am. Nucl. Soc. 44 (1983) 265.
- L. Li, K. Smith, B. Forget, Techniques for stabilizing coarse-mesh finite difference (CMFD) in methods of characteristics, in: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, Tennessee, 2015.
- M. Jarrett, B. Kochunas, A. Zhu, et al., Analysis of stabilization techniques for CMFD acceleration of neutron transport problems, Nucl. Sci. Eng. 184 (2) (2016) 208-227. https://doi.org/10.13182/NSE16-51
- M. Jarrett, B. Kelley, B. Kochunas, et al., Stabilization methods for CMFD acceleration, in: Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, TN, United States, 2015.
- D. Wang, S. Xiao, A linear prolongation approach to stabilizing CMFD, Nucl. Sci. Eng. 190 (1) (2018) 45-55. https://doi.org/10.1080/00295639.2017.1417347
- N.Z. Cho, G.S. Lee, C.J. Park, Partial current based CMFD acceleration of the 2D/1D fusion method for 3D whole-core transport, Trans. Am. Nucl. Soc. 88 (2003) 594.
- A. Zhu, M. Jarrett, Y. Xu, et al., An optimally diffusive Coarse Mesh Finite Difference method to accelerate neutron transport calculations, Ann. Nucl. Energy 95 (2016) 116-124. https://doi.org/10.1016/j.anucene.2016.05.004
- C. Hao, Y. Xu, T.J. Downar, Multi-level coarse mesh finite difference acceleration with local two-node nodal expansion method, Ann. Nucl. Energy 116 (2018) 105-113. https://doi.org/10.1016/j.anucene.2018.02.002
- S.C. Shaner, Transient Method of Characteristics via the Adiabatic, Theta, and Multigrid Amplitude Function Methods (Master thesis), Massachusetts Institute of Technology: Department of Nuclear Science and Engineering, 2014.
- N. Horelik, B. Herman, B. Forget, et al., Benchmark for evaluation and validation of reactor simulations (BEAVRS), in: International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering(M&C 2013), Sun Valley, ID, United States, 2013.
- R.D. Lawrence, Progress in nodal methods for the solution of the neutron diffusion and transport equations, Prog. Nucl. Energy 17 (3) (1986) 271-301. https://doi.org/10.1016/0149-1970(86)90034-X
- E.E. Lewis, N. Tsoulfanidis, M.A. Smith, et al., Benchmark on Deterministic Transport Calculations without Spatial Homogenization-MOX Fuel Assembly 3-D Extension Case, vol. 16, NEA/NSC/DOC, 2005. OECD/NEA, 2005.
- W. Boyd, Reactor Agnostic Multi-Group Cross Section Generation for Fine-Mesh Deterministic Neutron Transport Simulations (Ph.D. thesis), Massachusetts Institute of Technology: Department of Nuclear Science and Engineering, 2017.
- W. Boyd, N. Gibson, B. Forget, et al., An analysis of condensation errors in multi-group cross section generation for fine-mesh neutron transport calculations, Ann. Nucl. Energy 112 (2018) 267-276. https://doi.org/10.1016/j.anucene.2017.09.052
- G. Giudicelli, K. Smith, B. Forget, Generalized equivalence methods for 3D multi-group neutron transport, Ann. Nucl. Energy 112 (2018) 9-16. https://doi.org/10.1016/j.anucene.2017.09.024
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- Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh vol.207, pp.7, 2020, https://doi.org/10.1080/00295450.2021.1871995