참고문헌
- N.A. Anderson, Coupling RELAP5-3D and Fluent to analyze a Very High Temperature Reactor (VHTR) outlet plenum (Doctoral dissertation, Texas A&M University), 2006.
- D.L. Aumiller, E.T. Tomlinson, W.L. Weaver, An integrated relap5-3d and multiphase cfd code system utilizing a semi-implicit coupling technique, Nucl. Eng. Des. 216 (2002) 77-87. https://doi.org/10.1016/S0029-5493(01)00522-2
- R. Baviere, N. Tauveron, F. Perdu, E. Garre, S. Li, A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_ U. Preliminary validation on the Phenix Reactor Natural Circulation Test, Nucl. Eng. Des. 277 (2014) 124-137. https://doi.org/10.1016/j.nucengdes.2014.05.031
- D. Bertolotto, Coupling a System Code with Computational Fluid Dynamics for the Simulation of Complex Coolant Reactivity Effects, Lausanne, EPFL, 2011.
- D. Bertolotto, A. Manera, S. Frey, H.M. Prasser, R. Chawla, Single-phase mixing studies by means of a directly coupled CFD/system-code tool, Ann. Nucl. Energy 36 (2009) 310-316. https://doi.org/10.1016/j.anucene.2008.11.027
- F. D'Auria, J.L.G. Moreno, G.M. Galassi, D. Grgic, A. Spadoni, Three mile island unit 1 main steam line break three-dimensional neutronics/thermal-hydraulics analysis: application of different coupled codes, Nucl. Technol. 142 (2003) 180-204. https://doi.org/10.13182/nt03-a3383
- A.T. Edwards, T.P. O'brien, Studies of phenomena connected with the depressurization of water reactors, J. Brit. Nucl. Energy Soc 9 (2) (1970) 125-135.
- T.H. Fanning, J.W. Thomas, Nuclear Engineering Division, Advances in coupled safety modeling using systems analysis and high-fidelity methods. United States. https://doi.org/10.2172/982349.
- T.T. Feng, W.X. Tian, P. Song, D.L. Zhang, S.Z. Qiu, Transient characteristics analysis of water hammer phenomena based on coupling program, Atomic Energy Sci. Technol. 51 (2017) 1364-1370.
- D. Martelli, N. Forgione, G. Barone, I. Di Piazza, A. Del Nevo, Coupled Simulation of the NACIE Facility using the RELAP5 Thermal System Code and the CFD Ansys FLUENT Code, in: HLMC-2013, 2013, pp. 1-15.
- T.K.P.K. Francesco Cadinu, STUDY OF ALGORITHMIC REQUIREMENTS FOR A SYSTEM-TO-CFD COUPLING STRATEGY, 2014.
- M. Garcia, R. Tuominen, A. Gommlich, D. Ferraro, V. Valtavirta, et al., A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors, Ann. Nucl. Energy 139 (2020) 107213. https://doi.org/10.1016/j.anucene.2019.107213
- A. Geist, PVM: parallel virtual machine, A Users Guide & Tutorial for Networked Parallel Computing 92 (1994) 19-23.
- V.F. Gonzalez-Albuixech, G. Qian, M. Sharabi, M. Niffenegger, B. Niceno, N. Lafferty, Coupled RELAP5, 3D CFD and FEM analysis of postulated cracks in RPVs subjected to PTS loading, Nucl. Eng. Des. 297 (2016) 111-122. https://doi.org/10.1016/j.nucengdes.2015.11.032
- T.P. Grunloh, A. Manera, A novel domain overlapping strategy for the multiscale coupling of CFD with 1D system codes with applications to transient flows, Ann. Nucl. Energy 90 (2016) 422-432. https://doi.org/10.1016/j.anucene.2015.12.027
- T.P. Grunloh, A. Manera, A novel multi-scale domain overlapping CFD/STH coupling methodology for multi-dimensional flows relevant to nuclear applications, Nucl. Eng. Des. 318 (2017) 85-108. https://doi.org/10.1016/j.nucengdes.2017.03.027
- J.J. Jeong, S.K. Sim, C.H. Ban, C.E. Park, Assessment of the COBRA/RELAP5 code using the LOFT L2-3 large-break loss-of-coolant experiment, Ann. Nucl. Energy 24 (1997) 1171-1182. https://doi.org/10.1016/S0306-4549(97)00029-7
- J. Jimenez Escalante, V. Di Marcello, V. Sanchez Espinoza, Y. Perin, Application of the ATHLET/COBRA-TF thermal-hydraulics coupled code to the analysis of BWR ATWS, Nucl. Eng. Des. 321 (2017) 318-327. https://doi.org/10.1016/j.nucengdes.2016.10.001
- S. Kliem, R. Franz, Quick-look Report of the ROCOM Tests 1.1 and 1.2 Conducted within the OECD PKL2 Project, 2010.
- Y. Ku, Y. Tseng, J. Yang, S. Chen, J. Wang, C. Shin, Developments and applications of TRACE/CFD model of maanshan PWR pressure vessel, in: NURETH-16, 2015. Chicago, IL.
- H. Kyu Cho, Y.J. Cho, H.Y. Yoon, Heat structure coupling of CUPID and MARS for the multi-scale simulation of the passive auxiliary feedwater system, Nucl. Eng. Des. 273 (2014) 459-468. https://doi.org/10.1016/j.nucengdes.2014.03.017
- S.Y. Lee, J.J. Jeong, S.H. Kim, S.H. Chang, COBRA/RELAP5: a merged version of the COBRA-TF and RELAP5/MOD3 codes, Nucl. Technol. 99 (1992) 177-187. https://doi.org/10.13182/NT99-177
- W. Li, X. Wu, D. Zhang, G. Su, W. Tian, S. Qiu, Preliminary study of coupling CFD code FLUENT and system code RELAP5, Ann. Nucl. Energy 73 (2014) 96-107. https://doi.org/10.1016/j.anucene.2014.06.042
- X.J. Liu, X. Cheng, Sub-channel/system coupled code development and its application to SCWR-FQT loop, Nucl. Eng. Des. 285 (2015) 39-47. https://doi.org/10.1016/j.nucengdes.2015.01.007
- Y. Liu, H. Zhang, B.S. Jia, Research on coupling between RELAP5 and CFX codes, Atomic Energy Sci. Technol. 44 (2010) 304-308.
- D. Martelli, N. Forgione, G. Barone, W. Ambrosini, Validation of the coupled calculation between RELAP5 STH code and ansys FLUENT CFD code, 2013.
- D. Martelli, N. Forgione, G. Barone, A.D. Nevo, I. Di Piazza, M. Tarantino, Coupled simulations OF natural and forced circulation tests IN NACIE facility using RELAP5 and ANSYS FLUENT codes, in: Proceedings of the 2014 22nd International Conference on Nuclear Engineering (ICONE22), 2014 (Prague, Czech Republic).
- J. Ming, W. Guowei, W. Xianjuan, B. Yunqing, Z. Zhumin, L. Yazhou, Preliminary study of coupled Fluent and RELAP5 code for heat transfer of leadbased reactor, in: The 14th National Reactor Thermal Fluid Academic Conference of CHINA, 2015 (Beijing, China).
- A. Nava Dominguez, Y.F. Rao, T. Beuthe, Advances of the AC-DC code, a coupled computational tool to perform thermalhydraulic modeling of fuel bundles with annular fuel elements, Nucl. Eng. Des. 356 (2020) 110360. https://doi.org/10.1016/j.nucengdes.2019.110360
- A. Papukchiev, C. Geffray, M. Jeltsov, K. Kap, P. Kudinov, D. Grischenko, Multiscale analysis of forced and natural convection including heat tranfer phenomena in the TALL-3D experimental facility, in: Proc. Of NURETH-16, 2015 (Chicago, IL).
- A. Papukchiev, G. Lerchl, C. Waata, T. Frank, Extension of the simulation capabilities of the 1D system code ATHLET by coupling with the 3D CFD software package ANSYS CFX, in: The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), 2009 (Kanazawa City, Ishikawa Prefecture, Japan).
- I.K. Park, J.R. Lee, S.W. Lee, H.Y. Yoon, J.J. Jeong, An implicit code coupling of 1-D system code and 3-D in-house CFD code for multi-scaled simulations of nuclear reactor transients, Ann. Nucl. Energy 59 (2013) 80-91. https://doi.org/10.1016/j.anucene.2013.03.048
- Q. Peng, H.X. Yu, S. Vandroux, F. Perdu, W. Yang, Analytical study on coupling of CATHARE and TRIO_U code for nuclear reactor thermal-hydraulic analysis, Nucl. Power Eng. 34 (S1) (2013) 201-205.
- S. Kliem Thur, MAIN STEAM LINE BREAK ANALYSIS OF A VVER-440 REACTOR USING THE COUPLED THERMOHYDRAULICS SYSTEM/3D-NEUTRON KINETICS CODE DYN3D/ATHLET IN COMBINATION WITH THE CFD CODE CFX-4, 1999.
- R.R. Schultz, W.L. Weaver, Using the RELAP5-3D advanced systems analysis code with commercial and advanced CED software, in: The 11th Proceedings Of the International Conference On Nuclear Engineering (ICONE11), 2003.
- K.A. Smith, A.J. Baratta, G.E. Robinson, Coupled RELAP5 and CONTAIN accident analysis using PVM, Nucl. Saf. 36 (1995).
- G. Theodoridis, A. Papukchiev, D. Scholz, G. Lerchl, A New Data-Driven ATHLET-ANSYS CFD Coupling Method for Efficient Simulation of Nuclear Power Plant Circuits, in: International Conference on Nuclear Engineering (Vol. 45943, p. V004T10A047), American Society of Mechanical Engineers, 2014, July.
- M.J. Thurgood, T.E. Guidotti, G.A. Sly, J.M. Kelly, R.J. Kohrt, COBRA/TRAC - a thermal-hydraulics code for transient analysis of nuclear reactor vessels and primary coolant systems, Developmental Assessment and Data Comparisons 4 (1983).
- A. Toti, J. Vierendeels, F. Belloni, Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors, Ann. Nucl. Energy 103 (2017) 36-48. https://doi.org/10.1016/j.anucene.2017.01.002
- A. Toti, J. Vierendeels, F. Belloni, Extension and application on a pool-type test facility of a system thermal-hydraulic/CFD coupling method for transient flow analyses, Nucl. Eng. Des. 331 (2018) 83-96. https://doi.org/10.1016/j.nucengdes.2018.02.004
- E. Volpenhein, RELAP5-3D Coupling with STAR-CCM, 2013.
- L. Vyskocil, J. Macek, Coupling CFD code with system code and neutron kinetic code, Nucl. Eng. Des. 279 (2014b) 210-218. https://doi.org/10.1016/j.nucengdes.2014.02.011
- T. Watanabe, Y. Anoda, M. Takano, System-CFD coupled simulations of flow instability in steam generator U tubes, Ann. Nucl. Energy 70 (2014) 141-146. https://doi.org/10.1016/j.anucene.2014.02.029
- L. Xing, H. Yeung, Y. Geng, Y. Cao, J. Shen, Study on hydrodynamic slug flow mitigation with wavy pipe using a 3D-1D coupling approach, Comput. Fluids 99 (2014) 104-115. https://doi.org/10.1016/j.compfluid.2014.04.023
- Y. Yan, Rizwan-uddin, COUPLED CFD-SYSTEM-CODE SIMULATION OF A GAS COOLED REACTOR, American Nuclear Society, 2011a.
- Y. Yan, Development of a coupled CFD-system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors (Doctoral dissertation, University of Illinois at Urbana-Champaign), 2012.
- B. Yang, J. Long, H. Ninokata, et al., Subchannel analysis-current practice and development for the future, Nucl. Energy Des. (2020). In preparation.
- D. Ziabletsev, M. Avramova, K. Ivanov, Development of pressurized water reactor integrated safety analysis methodology using multilevel coupling algorithm, Nucl. Sci. Eng. 148 (2004) 414-425. https://doi.org/10.13182/nse04-a2467
- D.L. Aumiller, E.T. Tomlinson, R.C. Bauer, A coupled RELAP5-3D/CFD methodology with a proof-of-principle calculation, Nucl. Eng. Des. 205 (1/2) (2001) 83-90. https://doi.org/10.1016/S0029-5493(00)00370-8
피인용 문헌
- MHD R&D Activities for Liquid Metal Blankets vol.14, pp.20, 2021, https://doi.org/10.3390/en14206640