IMPLEMENTATION OF QUADRATIC AXIAL TRIAL FUNCTIONS IN THE HIGH-FIDELITY TRANSPORT CODE PROTEUS-MOC

Guangchun Zhang; Won Sik Yang

doi:10.1051/epjconf/202124703015

All issues

Volume 247 (2021)

EPJ Web Conf., 247 (2021) 03015

References

Open Access

Issue		EPJ Web Conf. Volume 247, 2021 PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future


Article Number		03015
Number of page(s)		8
Section		Deterministic Transport
DOI		https://doi.org/10.1051/epjconf/202124703015
Published online		22 February 2021

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A.M. Lafleche, M.A. Smith and C. Lee, “PROTEUS-MOC: A 3D Deterministic Solver Incorporating 2D Method of Characteristics,” Proc. Mathematics and Computation (M&C 2013), Sun Valley, Idaho, May 5-9, 2013. [Google Scholar]
G. Zhang, A. Hsieh, W.S. Yang and Y. S. Jung, “Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC,” Nucl. Sci. Eng. 193, pp. 828–853 (2019). [Google Scholar]
M.A. Smith, E.E. Lewis, and B.-C. Na, “Benchmark on Deterministic Transport Calculations Without Spatial Homogenization: MOX Fuel Assembly 3-D Extension Case,” NEA/NSC/DOC(2005)16, Organization for Economic Co-operation and Development/Nuclear Energy Agency (2005). [Google Scholar]

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[1] N.Z. Cho, G.S. Lee and C.J. Park, “Refinement of the 2-D/1-D Fusion Method for 3-D Whole Core Transport Calculation,” Trans. Am. Nucl. Soc. 87, pp. 417 (2002). [Google Scholar]

[2] H.G. Joo, J.Y. Cho, K.S. Kim, C.C. Lee and S.Q. Zee, “Methods and Performance of a Three-Dimensional Whole-Core Transport Code DeCART,” Proc. Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments (PHYSOR-2004), Chicago, Illinois, April 25-29, 2004. [Google Scholar]

[3] M. Hursin, “Full Core, Heterogeneous, Time Dependent Neutron Transport Calculations with the 3D Code DeCart,” PhD Thesis, University of California, Department of Nuclear Engineering, Berkeley (2010). [Google Scholar]

[4] B.W. Kelly and E.W. Larsen, “2D/1D Approximations to the 3D Neutron Transport Equation. I: Theory,” Proc. Mathematics and Computation (M&C 2013), Sun Valley, Idaho, May 5-9, 2013. [Google Scholar]

[5] M.A. Smith, D. Kaushik, A. Wollaber, W.S. Yang, and B. Smith, “New Neutronics Analysis Tool Development at Argonne National Laboratory,” Proc. of Int. Conf. on Fast Reactors and Related Fuel Cycles (FR09), Kyoto, Japan, December 7-11, 2009. [Google Scholar]

[6] G. Gunow, S. Shaner, B. Forget and K. Smith, “Reducing 3D MOC Storage with Axial on the Fly Ray Tracing,” Proc. PHYSOR 2016, May 1-5, 2016, Sun Valley, Idaho (2016). [Google Scholar]

[7] A.M. Lafleche, M.A. Smith and C. Lee, “PROTEUS-MOC: A 3D Deterministic Solver Incorporating 2D Method of Characteristics,” Proc. Mathematics and Computation (M&C 2013), Sun Valley, Idaho, May 5-9, 2013. [Google Scholar]

[8] G. Zhang, A. Hsieh, W.S. Yang and Y. S. Jung, “Consistent pCMFD Acceleration Schemes of the Three-Dimensional Transport Code PROTEUS-MOC,” Nucl. Sci. Eng. 193, pp. 828–853 (2019). [Google Scholar]

[9] M.A. Smith, E.E. Lewis, and B.-C. Na, “Benchmark on Deterministic Transport Calculations Without Spatial Homogenization: MOX Fuel Assembly 3-D Extension Case,” NEA/NSC/DOC(2005)16, Organization for Economic Co-operation and Development/Nuclear Energy Agency (2005). [Google Scholar]