Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform

References

• Chen P, Zhang SC, Zhang YC. Performance analysis of PWR fuel assembly and fuel element. Harbin, China: Harbin Engineering University Press; 2020.
   Google Scholar
• Li Q, Chen J, Jiao YJ, et al. Research on the resistance characteristics of rod bundles channels with 5×5 mixing grid. Nucl Power Eng. 2015;36(2):28–32.
   Google Scholar
• Wei ZL, Zhang Y, Liu ST, et al. Numerical simulation of mixed turbulence in rod bundles channels with lattice. Nucl Power Eng. 2015;36(4):158–162.
   Google Scholar
• Qiao L Structured grid based on CFD Study of 5 ×5 fuel assembly flow field [ Master’s Thesis]. Guangzhou, China: South China University of Technology; 2015.
   Google Scholar
• Lu YB. Research on CFD method for thermal-hydraulic modeling of fuel assembly [ Master’s Thesis]. Shanghai, China: Shanghai Jiao Tong University; 2018.
   Google Scholar
• Yin Q. Water at numerical study on flow and heat transfer characteristics in 5×5 fuel bundles [ Master’s Thesis]. Dalian, China: Dalian University of Technology; 2021.
   Google Scholar
• Han B, Zhu XL, Yang BW, et al. Verification and Validation of CFD and its application in PWR fuel assembly. Prog Nucl Energy. 2022;154:104485. doi: 10.1016/j.pnucene.2022.104485
   Web of Science ®Google Scholar
• Li X, Chen DQ, Hu L. Numerical investigation on mixing performance in rod bundle with spacer grid based on anisotropic turbulent mixing model. Int J Heat Mass Transfer. 2019;130:843–856. doi: 10.1016/j.ijheatmasstransfer.2018.10.121
   Web of Science ®Google Scholar
• Chen GL, Wang JJ, Zhang ZJ, et al. Distributed-parallel CFD computation for all fuel assemblies in PWR core. Ann Nucl Energy. 2020;141:107340. doi: 10.1016/j.anucene.2020.107340
   Web of Science ®Google Scholar
• Tian ZH, Yang LX, Han S, et al. Numerical investigation on the flow characteristics in a 17 × 17 full-scale fuel assembly. Energies. 2020;13(2):397.
   Web of Science ®Google Scholar
• Hirdaris SE, Cheng YF, Shallcross P, et al. Considerations on the potential use of nuclear small modular reactor (SMR) Technology for Merchant marine propulsion. Ocean Eng. 2014;79(1):101–130.
   Google Scholar
• Liu Y, Zhao Z, Wang Y, Zhao F, Lu D and Cao Q. (2023). Dynamic response of a multi-point mooring cylindrical floating nuclear power platform carrying a small-scale reactor. Ocean Engineering, 267 113121 10.1016/j.oceaneng.2022.113121
   Web of Science ®Google Scholar
• Murata H, Sawada K, Kobayashi M. Experimental investigation of Natural convection in a core of a marine reactor in rolling motion. J Nucl Sci Tech. 2000;37(6):509–517. doi: 10.1080/18811248.2000.9714924
   Web of Science ®Google Scholar
• Iyori I, Aya I, Murata H, et al. Natural circulation of integrated-type marine reactor at inclined attitude. Nucl Eng Des. 1987;99:423–430. doi: 10.1016/0029-5493(87)90138-5
   Web of Science ®Google Scholar
• Yang Y. Study on thermal coupling of subcooled boiling nuclei in typical channels under rolling conditions [ Master’s Thesis]. Chongqing, China: Chongqing University; 2016.
   Google Scholar
• Xu S, Pan LM. Numerical simulation of flow and heat transfer in rod bundle channels under rolling conditions. Proceedings of the 14th National Reactor Thermal Fluid Academic Conference; 2015 Sept 23-25; Beijing, China. p. 292–296.
   Google Scholar
• Tang H. Numerical simulation of flow field in 3×3 rod bundles channels under vertical and inclined conditions. Nucl Power Eng. 2017;38(S1):45–48.
   Google Scholar
• Movaffagh M, Abbasi M, Zolfaghari A. CFD investigation of PWR channel shapes effects during rolling motion under normal and accident condition. Ann Nucl Energy. 2023;181:109574. doi: 10.1016/j.anucene.2022.109574
   Web of Science ®Google Scholar
• Pfrogner RW.CTF PWR core modeling and validation applicable to High Burnup High Enrichment (HBHE) Fuel [ Master’s Thesis]. Raleigh, North Carolina, USA: North Carolina State University; 2023.
   Google Scholar
• Lee YG, Park IW. Numerical evaluation of coolability limits of external reactor vessel cooling using an Improved thermal-hydraulic System analysis code. In J Energy Research. 2023;2023:2375012. doi: 10.1155/2023/2375012
   Web of Science ®Google Scholar
• Li X, Wang H, Wang QL, et al. Experimental study on velocity distribution in rod bundle channels under flow fluctuation. J Phys Conf Ser. 2023;2441(1):012061.
   Google Scholar
• Zhu XX, Wang ZG, Xu CD, et al. Experimental investigations and numerical studies of two-phase countercurrent flow limitation in a pressurized water reactor: a review. Energies. 2023;16(3):1487.
   Web of Science ®Google Scholar
• Chandra L, Roelofs F, Houkema M, et al. A stepwise development and validation of a RANS based CFD modelling approach for the hydraulic and thermal-hydraulic analyses of liquid metal flow in a fuel assembly. Nucl Eng Des. 2009;239(10):1988–2003.
   Web of Science ®Google Scholar
• Gao PZ, Pang FG, Wang ZX. Mathematical model of primary circuit coolant of nuclear power plant affected by marine conditions. J Harbin Eng Univ. 1997;1:26–29.
   Google Scholar
• Yang J, Jia BS, Yu JY. Analysis of Natural circulation capability of core cooling System under harmonic ocean conditions. Chinese J Nucl Sci Eng. 2002;3:199–203+209.
   Google Scholar
• Zhang HL. Hydrodynamic performance analysis of a deepwater cylindrical drilling platform in the South China Sea [ Master’s Thesis]. Shanghai, China: Shanghai Jiao Tong University; 2019.
   Google Scholar
• Zhao ZW Study on dynamic response of multi-point mooring cylindrical floating nuclear power platform with the effect of wind, wave and current [ Master’s Thesis]. Beijing, China: North China Electric Power University; 2022.
   Google Scholar
• Bieder U, Falk F, Fauchet G. LES analysis of the flow in a simplified PWR assembly with mixing grid. Prog Nucl Energy. 2014;75:15–24. doi: 10.1016/j.pnucene.2014.03.014
   Web of Science ®Google Scholar
• Qu WH, Yao WY, Xiong JB, et al. Experimental study of pressure loss in a 5 × 5–rod bundle with the mixing vane spacer grid. Front Energy Res. 2021;9:675494. doi: 10.3389/fenrg.2021.675494
   Web of Science ®Google Scholar