References
- J.Y. Cho, H.G. Joo, K.S. Kim, S.Q. Zee, Three-dimensional heterogeneous whole core transport calculation employing planar MOC solutions, Trans. Am. Nucl. Soc. 87 (2002) 234-236.
- N.Z. Cho, G.S. Lee, C.J. Park, Refinement of the 2D/1D fusion method for 3D whole core transport calculation, Trans. Am. Nucl. Soc. 87 (2002) 417-420.
- H.G. Joo, J.Y. Cho, K.S. Kim, C.C. Lee, S.Q. Zee, Methods and Performance of a Three-Dimensional Whole Core Transport Code DeCART. Proc. PHYSPR, American Nuclear Society, CD-ROM, 2004, 2004, Chicago, April 25-29, 2004.
- G.S. Lee, N.Z. Cho, 2D/1D fusion method solutions of the three-dimensional transport OECD benchmark problems C5G7 MOX, Prog. Nucl. Energy 48 (2006) 410-423. https://doi.org/10.1016/j.pnucene.2006.01.010
- J.Y. Cho, K.S. Kim, C.C. Lee, et al., Axial SPN and radial MOC coupled whole core transport calculation, J. Nucl. Sci. Technol. (Tokyo, Jpn.) 44 (2007) 1156-1171. https://doi.org/10.1080/18811248.2007.9711359
- Y. Jung, H.G. Joo, Decoupled Planar MOC Solution for Dynamic Group Constant Generation in Direct Three-Dimensional Core Calculations. Proc. M&C, vol. 44, Saratoga Springs, NY. USA., 2009. May 3-7.
- Q. Shen, Y. Wang, D. Jabaay, et al., Transient analysis of C5G7-TD benchmark with MPACT, Ann. Nucl. Energy 125 (2018) 107-120. MAR.). https://doi.org/10.1016/j.anucene.2018.10.049
- B. Wang, Z. Liu, J. Chen, et al., A modified predictor-corrector quasi-static method in NECP-X for reactor transient analysis based on the 2D/1D transport method, Prog. Nucl. Energy 108 (Sep) (2018) 122-135. https://doi.org/10.1016/j.pnucene.2018.05.014
- J. Ma, C. Hao, L. Liu, et al., Perturbation theory-based whole-core eigenvalue sensitivity and uncertainty (SU) analysis via a 2D/1D transport code, Sci. Technol.Nucl. Install. 2020 (2020) 13. Article ID 9428580.
- B.W. Kelly, E.W. Larsen, 2D/1D Approximations to the 3D Neutron Transport Equation I: Theory. Proc. M&C, 2013, Sun Valley, ID, USA, 2013. May 5-9.
- M. Jarrett, B. Kochunas, et al., Progress in Characterizing 2D/1D Accuracy in MPACT. Proc. M&C, 2017. Jeju, Korea. April 16-20.
- S.G. Hong, K.S. Kim, J.S. Song, Fourier convergence analysis of the rebalance methods for discrete ordinates transport equations in eigenvalue problems, Nucl. Sci. Eng. 164 (1) (2010) 33-52. https://doi.org/10.13182/NSE09-18
- A. Zhu, M. Jarret, Y. Xu, B. Kochunas, E. Larsen, T. Downar, 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
- B.W. Kelly, E.W. Larsen, A consistent 2D/1D approximation to the 3D neutron transport equation, Nucl. Eng. Des. 295 (2015) 598-614. https://doi.org/10.1016/j.nucengdes.2015.07.026
- K.P. Keady, E.W. Larsen, Stability of SN k-eigenvalue iterations using CMFD acceleration, in: Proc. Int. Conf. On Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, American Nuclear society, Nashville, Tennessee, USA, 2015. April 19-23.
- Y. Chan, S. Xiao, Convergence study of variants of CMFD acceleration schemes for fixed source neutron transport problems in 2D cartesian geometry with Fourier analysis, Ann. Nucl. Energy 134 (2019) 273-283. https://doi.org/10.1016/j.anucene.2019.06.021
- Y. Chan, S. Xiao, Convergence study of CMFD and lpCMFD acceleration schemes for k-eigenvalue neutron transport problems in 2D cartesian geometry with Fourier analysis, Ann. Nucl. Energy 133 (2019) 327-337. https://doi.org/10.1016/j.anucene.2019.05.035
- L. Jain, Prabhakaran, et al., Convergence study of CMFD based acceleration schemes for multi-group transport calculations with fission source using Fourier analysis, Ann. Nucl. Energy 160 (2021) (2021), 108314.
- L. Jain, Karthikeyan, et al., Comparative studies of iterative methods for solving the optimally diffusive coarse mesh finite difference accelerated transport equation, Ann. Nucl. Energy 157 (2021) (2021), 108211.
- B. Kong, K. Zhu, H. Zhang, C. Hao, J. Guo, F. Li, A discontinuous Galerkin finite element method based axial SN for the 2D/1D transport method, Prog. Nucl. Energy 152 (2022), 104391. October.
- X. Zhou, Z. Liu, L. Cao, H. Wu, Convergence analysis for the CMFD accelerated 2D/1D neutron transport method based on Fourier analysis, Nucl. Sci. Eng. 17 (2022), 108982.
- Y. Chan, S. Xiao, A linear prolongation CMFD acceleration for two-dimensional discrete ordinate k-eigenvalue neutron transport calculation with pinresolved mesh using discontinuous Galerkin finite element method, Ann. Nucl. Energy 154 (2021), 108103.
- 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
- D. Wang, S. Xiao, Stabilizing CMFD with Linear Prolongation, PHYSOR, Cancun, Mexico, 2018. April 22-26.
- K. Paul, E. Nicholas, et al., OpenMC: a state-of-the-art Monte Carlo code for research and development, Ann. Nucl. Eng. 82 (2015) 90-97. https://doi.org/10.1016/j.anucene.2014.07.048
- J.J. Klingensmith, Y.Y. Azmy, J.C. Gehin, et al., Tort solutions to the three-dimensional MOX benchmark, 3D extension C5G7MOX, Prog. Nucl. Energy 48 (5) (2006) 445-455. https://doi.org/10.1016/j.pnucene.2006.01.011
- M.A. Smith, et al., Benchmark on Deterministic Transport Calculations without Homogenization, Nuclear energy agency organization for economic cooperation and development (NEA-OECD), 2003.
- B. Kong, K. Zhu, et al., Convergence study of DGFEM SN based 2D/1D coupling method for solving neutron transport k-eigenvalue problems with Fourier analysis, Ann. Nucl. Energy 177 (2022), 109327.
- Hyun Chul Lee, et al., Fourier convergence analysis of two-dimensional/one-dimensional coupling methods for the three-dimensional neutron diffusion eigenvalue problems, Nucl. Sci. Eng.J. Am. Nucl. Soc. 156 (1) (2014) 74-85. https://doi.org/10.13182/NSE06-32