SUN Yumeng,LI Jie,WEI Zonglan,et al.Assessment of jet turbulence model of pressure vessels inset pipe based on direct numerical simulation[J].Acta Scientiarum Naturalium Universitatis Sunyatseni,2024,63(04):88-96.
SUN Yumeng,LI Jie,WEI Zonglan,et al.Assessment of jet turbulence model of pressure vessels inset pipe based on direct numerical simulation[J].Acta Scientiarum Naturalium Universitatis Sunyatseni,2024,63(04):88-96. DOI: 10.13471/j.cnki.acta.snus.ZR20240058.
Assessment of jet turbulence model of pressure vessels inset pipe based on direct numerical simulation
The open-source software Nek5000, based on the spectral element method, was used to conduct direct numerical simulation (DNS) of the pressure vessel inset pipe. A simplified 1/3 scale pressure vessel with a main pipe
Re
of 63 700, a downcomer section
Re
of 14 014, and a flowing medium of sodium iodide solution were used for the simulations. Turbulent statistics were conducted on common physical quantities, leading to the construction of a highly accurate turbulent flow database. Fluent was used to conduct an adaptive assessment of common wall functions and turbulent models, with assessment criteria based on velocity, turbulent kinetic energy, and turbulent viscosity. The findings indicate that the Stress-
ω
model is optimal for the rising section, whereas the Standard
FISCHER P, LOTTES J, TUFO H, 2007. Nek5000[R]. Argonne, IL (United States):Argonne National Lab(ANL).
LUCAS D, BESTION D, BODÈLE E, et al, 2009. An overview of the pressurized thermal shock issue in the context of the NURESIM project[J]. Sci Technol Nuclear Install,2009:583259.
MENG T, ZHAO F, CHENG K, et al, 2019. Numerical study of flow and heat transfer characteristic of space gas-cooled nuclear reactor core[J]. Atomic Energy Sci Tech, 53(7): 1264.
MULLOY J R, JOHN P, 2018. A RANS analysis of pressurized thermal shock phenomena in nuclear reactor geometries using star CCM+[D].Texas:Texas A&M University.
SHARABI M, GONZÁLEZ-ALBUIXECH V F, LAFFERTY N, et al, 2016. Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel[J]. Nucl Eng Des, 299: 136-145.
ZHANG Q, LIU L, ZENG Y, et al, 2022. Numerical simulation of inherent boric mixing phenomenon inside reactor annular down-comer[J]. Prog Nucl Energy, 148: 104230.
ZENG Y, ZHANG Q, CHEN H, et al, 2023. Numerical investigation of the external emergency coolant transportation inside reactor annular down-comer[J]. Ann Nucl Energy, 187: 109780.