Verification of neutronics and thermal-hydraulic coupled system with pin-by-pin calculation for PWR core

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참고문헌 (36)

1. R. Szilard, "The Consortium for Advanced Simulation of Light Water Reactors", Englarged Halden Programme Group Meeting (2011)
2. Christian Chauliac, "NURESIM – A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysis", Nuclear Engineering and Design, 241(9), pp.3416~3426 (2011), Elsevier BV[DOI]
3. W. Yang, "Research progress of China virtual reactor (CVR1.0)", Atomic Energy Sci. Technol, 53(10), pp.1821~1832 (2019)[DOI]
4. Cody J. Permann, "MOOSE: Enabling massively parallel multiphysics simulation", SoftwareX, 11, pp.100430~ (2020), Elsevier BV[DOI]
5. Yaqi Wang, "Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application", Nuclear Technology, 207(7), pp.1047~1072 (2021), Informa UK Limited[DOI]
6. Richard L. Williamson, "BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms", Nuclear Technology, 207(7), pp.954~980 (2021), Informa UK Limited[DOI]
7. Derek R. Gaston, "Physics-based multiscale coupling for full core nuclear reactor simulation", Annals of Nuclear Energy, 84, pp.45~54 (2015), Elsevier BV[DOI]
8. Ulrich Rohde, "The reactor dynamics code DYN3D – models, validation and applications", Progress in Nuclear Energy, 89, pp.170~190 (2016), Elsevier BV[DOI]
9. PARCS: A Multi-Dimensional Two-Group Reactor Kinetics Code Based on the Nonlinear Analytic Nodal method, "T.J. Downar", PURDUE UNIVERSITY SCHOOL OF NUCLEAR ENGINEERING, ~, pp.PU (1998), NE-98-26
10. Maria Pusa, "Uncertainty analysis of assembly and core-level calculations with application to CASMO-4E and SIMULATE-3", Annals of Nuclear Energy, 104, pp.124~131 (2017), Elsevier BV[DOI]
11. A. C. M. Alvim, "Improved neutron leakage treatment on nodal expansion method for PWR reactors", Int. J. Math.Comput. Phys.Electr. Comput. Eng, 6(3), pp.228~231 (2012), World academy of science, engineering and technology
12. S.K. Hall, "The implementation of a simplified spherical harmonics semi-analytic nodal method in PANTHER", Annals of Nuclear Energy, 57, pp.280~293 (2013), Elsevier BV[DOI]
13. R. D. Lawrence, "A Nodal Green’s Function Method for Multidimensional Neutron Diffusion Calculations", Nuclear Science and Engineering, 76(2), pp.218~231 (1980), Informa UK Limited[DOI]
14. W. B. Zhao, "A simplified two-node coarse-mesh finite difference method for pin-with calculation with Sp3", Eur. Phys. J.Conf, 247(6), pp.02023~ (2021)
15. Wenbo Zhao, "A nodal method based on CMFD for pin-by-pin SP3 calculation", Annals of Nuclear Energy, 167, pp.108849~ (2022), Elsevier BV[DOI]
16. Chuntao Tang, "Development and Verification of an SP3 Code Using Semi-Analytic Nodal Method for Pin-by-Pin Calculation", Journal of Physical Science and Application, 7(2), pp.10~17 (2017), David Publishing Company
17. Yunzhao Li, "A three-dimensional PWR-core pin-by-pin analysis code NECP-Bamboo2.0", Annals of Nuclear Energy, 144, pp.107507~ (2020), Elsevier BV[DOI]
18. William Boyd, "The OpenMOC method of characteristics neutral particle transport code", Annals of Nuclear Energy, 68, pp.43~52 (2014), Elsevier BV[DOI]
19. Yuxuan Liu, "Validation of Pin-Resolved Reaction Rates, Kinetics Parameters, and Linear Source MOC in MPACT", Nuclear Science and Engineering, 195(1), pp.50~68 (2020), Informa UK Limited[DOI]
20. C. Zhao, "A new numerical nuclear reactor neutronics code SHARK", Front. Energy Res, (9), pp.784247~ (2021)
21. Yuxuan Liu, "Improved MPACT energy deposition and explicit heat generation coupling with CTF", Annals of Nuclear Energy, 152, pp.107999~ (2021), Elsevier BV[DOI]
22. Z.Y. Liu, "An internal parallel coupling method based on NECP-X and CTF and analysis of the impact of thermal-hydraulic model to the high-fidelity calculations", Ann. Nucl. Energy, (146), pp.107645~ (2020)
23. Diego Ferraro, "OECD", NRC PWR MOX, SUBCHANFLOW, pp.Annals of Nuclear Energy, 2020[DOI]
24. NEACRP 3-D LWR Core Transient Benchmarks, "H. Finnemann", OECD, 1993, NEA[DOI]
25. Pressurised Water Reactor MOX, "UO2 Core Transient Benchmark (Final Report)", K. Tomasz, 2007, NEA[DOI]
26. J.J. Pan, "Development of Whole CORe Thermal Hydraulic Analysis Code CORTH", M&C 2017 Internaltional Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (2017)
27. I. Toumi, "FLICA-4: a three-dimensional two-phase flow computer code with advanced numerical methods for nuclear applications", Nuclear Engineering and Design, 200(1-2), pp.139~155 (2000), Elsevier BV[DOI]
28. K. Ren, "Implementation of the LAX-Wendroff Method in Cobra-TF for Solving Two-phase Flow Transport Equations", ICAPP (2016)
29. Zhigang Li, "Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core", Journal of Nuclear Engineering and Radiation Science, 7(3), pp.034504~ (2021), ASME International[DOI]
30. Zhigang Li, "Development and verification of PWR core transient coupling calculation software", Nuclear Engineering and Technology, 53(11), pp.3653~3664 (2021), 한국원자력학회[DOI]
31. M.P. Kinght, "Derivation of a refined PANTHER solution to the NEACRP PWR rod-ejection transient", Proc.Jt.Int.Conf.Math. Method, (1), pp.302~313 (1997)
32. Deokjung Lee, "Multi-group SP 3 approximation for simulation of a three-dimensional PWR rod ejection accident", Annals of Nuclear Energy, 77, pp.94~100 (2015), Elsevier BV[DOI]
33. Mathieu Hursin, "Analysis of the Core Power Response during a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code", Nuclear Science and Engineering, 170(2), pp.151~167 (2012), Informa UK Limited[DOI]
34. Muhammad Imron, "Development and verification of open reactor simulator ADPRES", Annals of Nuclear Energy, 133, pp.580~588 (2019), Elsevier BV[DOI]
36. Dongyong Wang, "Description and verification of KYLIN-V2.0 lattice physics code", Nuclear Engineering and Design, 379, pp.111232~ (2021), Elsevier BV[DOI]

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