참고문헌
- G. Prasser, T. Grunwald, S. Hohne, et al., Coolant mixing in a pressurized water reactor: deboration transients, steam-line breaks, and emergency core cooling injection, Nucl. Technol. 143 (1) (2003) 37-56. https://doi.org/10.13182/NT03-A3396
- R.J. Hertlein, K. Umminger, S. Kliem, et al., Experimental and numerical investigation of boron dilution transients in pressurized water reactors, Nucl. Technol. 141 (1) (2003) 88-107. https://doi.org/10.13182/NT03-A3353
- R. Ulrich, H. Bengt, K. Soeren, et al., The European Project FLOMIX-R: Fluid Mixing and Flow Distribution in the Reactor Circuit, Final Summary Report. Report FZR, vol. 432, Rossendorf, Dresden, Germany, 2005.
- T. Hohne, S. Kliem, U. Bieder, Modeling of a buoyancy-driven flow experiment at the ROCOM test facility using the CFD codes CFX-5 and TRIO U, Nucl. Eng. Des. 236 (12) (2006) 1309-1325. https://doi.org/10.1016/j.nucengdes.2005.12.005
- Kim Kihwan, Dong-Jin, In-Cheol Euh, Chu, et al., Experimental study of the APR+ reactor core flow and pressure distributions under 4-pump running conditions, Nucl. Eng. Des. 265 (2013) 957-966. https://doi.org/10.1016/j.nucengdes.2013.07.021
- T.V. Dury, B. Hemstrom, S.V. Shepel, CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies, Nucl. Eng. Des. 238 (3) (2008) 577-589. https://doi.org/10.1016/j.nucengdes.2007.02.038
- G. Pochet, M. Haedens, C.R. Schneidesch, et al., CFD simulations of the flow mixing in the lower plenum of PWR's, Nucl. Phys. 2 (2) (2012) 160-168. https://doi.org/10.1016/0029-5582(56)90042-6
- S.K. Kang, Y.A. Hassan, Computational fluid dynamics (CFD) round robin benchmark for a pressurized water reactor (PWR) rod bundle, Nucl. Eng. Des. 301 (2016) 204-231. https://doi.org/10.1016/j.nucengdes.2016.03.007
- S. Bhattacharjee, G. Ricciardi, S. Viazzo, Comparative study of the contribution of various PWR spacer grid components to hydrodynamic and wall pressure characteristics, Nucl. Eng. Des. 317 (2017) 22-43. https://doi.org/10.1016/j.nucengdes.2017.03.011
- M. Wang, L. Bai, L. Wang, et al., Thermal hydraulic and stress coupling analysis for AP1000 pressurized thermal shock (PTS) study under SBLOCA scenario, Appl. Therm. Eng. 122 (2017) 158-170. https://doi.org/10.1016/j.applthermaleng.2017.04.106
- M.T. Kao, C.Y. Wu, C.C. Chieng, et al., CFD analysis of PWR core top and reactor vessel upper plenum internal subdomain models, Nucl. Eng. Des. 241 (10) (2011) 4181-4193. https://doi.org/10.1016/j.nucengdes.2011.08.007
- Y.B. Xu, C. Michael, K. Yuan, et al., Study of impact of the AP1000 reactor vessel upper internals design on fuel performance, Nucl. Eng. Des. 252 (2012) 128-134. https://doi.org/10.1016/j.nucengdes.2012.06.036
- Y.M. Chao, Y.J. Zhai, L.X. Yang, et al., Thermal Hydraulics Characteristics Simulation of CPR1000 Using CFD Method, Proceeding of ICONE-21, Chengdu, China, 2013. ICONE21-16591.
- T. Hohne, G. Grunwald, U. Rohde, Coolant mixing in pressurized water reactors, in: Proceeding of the 8th AER Symposium on VVER Reactor Physics and Safety, Bystrice and Pernctejnem, Czech Republic, 1998. FZR-237.
- ANSYS CFX Help, Computational Fluid Dynamics, Release 18.2, ANSYS Inc. Copyright © 2011 Elsevier BV All rights reserved.
- Westinghouse Electric Co LLC, Wastinghouse AP1000 Design Control Document, vol. 19, Revision, Butler County, Pennsylvania, U.S.A, 2011.
- Hao L. L., Chen H., Qiu S. C., Sensitivity analysis of turbulence models for the core inlet flow distribution of PWR. Proceedings of the 2018 26th International Conference on Nuclear Engineering, July 22-26, 2018, London, England.
피인용 문헌
- Experimental study on flow distribution and mixing at the core inlet of double-loop small module reactor vol.152, 2021, https://doi.org/10.1016/j.anucene.2020.108010