Direct Numerical Simulation of Low and Unitary Prandtl Number Fluids in Reactor Downcomer Geometry

被引:2
作者
Tai, Cheng-Kai [1 ]
Nguyen, Tri [2 ]
Iskhakov, Arsen S. [1 ]
Merzari, Elia [2 ]
Dinh, Nam T. [1 ]
Bolotnov, Igor A. [1 ]
机构
[1] North Carolina State Univ, Campus Box 7909, Raleigh, NC 27695 USA
[2] Penn State Univ, 206 Hallowell Bldg, University Pk, PA 16802 USA
关键词
Direct numerical simulation; vertical mixed convection; low-Prandtl-number fluids; downcomer; TURBULENT MIXED CONVECTION; HEAT-TRANSFER; CHANNEL FLOW; BUOYANCY; DNS; MODEL; PIPE;
D O I
10.1080/00295450.2023.2213286
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Mixed convection of low and unitary Prandtl fluids in a vertical passage is fundamental to passive heat removal in liquid metal and gas-cooled advanced reactor designs. Capturing the influence of buoyancy in flow and heat transfer in engineering analysis is hence a cornerstone to the safety of the next-generation reactor. However, accurate prediction of the mixed convection phenomenon has eluded current turbulence and heat transfer modeling approaches, yet further development and validation of modeling methods is limited by a scarcity of high-fidelity data pertaining to reactor heat transfer. In this work, a series of direct numerical simulations was conducted to investigate the influence of buoyancy on descending flow of liquid sodium, lead, and unitary Prandtl fluid in a differentially heated channel that represents the reactor downcomer region. From time-averaged statistics, flow-opposing/aiding buoyant plumes near the heated/cooled wall distort the mean velocity distribution, which gives rise to promotion/suppression of turbulence intensity and modification of turbulent shear stress and heat flux distribution. Frequency analysis of time series also suggests the existence of large-scale convective and thermal structures rising from the heated wall. As a general trend, fluids of lower Prandtl number were found to be more susceptible to the buoyancy effect due to stronger differential buoyancy across the channel. On the other hand, the effectiveness of convective heat transfer of the three studied fluids showed a distinct trend against the influence of buoyancy. Physical reasoning on observation of the Nusselt number trend is also discussed.
引用
收藏
页码:1097 / 1118
页数:22
相关论文
共 35 条
  • [1] Direct numerical simulation of turbulent forced and mixed convection of LBE in a bundle of heated rods with P/D=1.4
    Angeli, D.
    Fregni, A.
    Stalio, E.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2019, 355
  • [2] Bolotnov I., 2021, Challenge Problem 1: Benchmark Specifications for the Direct Numerical Simulation of Canonical Flows
  • [3] DISTORTION OF TURBULENT VELOCITY AND TEMPERATURE PROFILES ON HEATING, FOR MERCURY IN A VERTICAL PIPE
    BUHR, HO
    HORSTEN, EA
    CARR, AD
    [J]. JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 1974, 96 (02): : 152 - 158
  • [4] BYRNE J. E., MECH ENG S HEAT MASS
  • [5] VERTICAL TUBE AIR-FLOWS IN THE TURBULENT MIXED CONVECTION REGIME CALCULATED USING A LOW-REYNOLDS-NUMBER K-APPROXIMATELY-EPSILON MODEL
    COTTON, MA
    JACKSON, JD
    [J]. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1990, 33 (02) : 275 - 286
  • [6] The influence of low Prandtl numbers on the turbulent mixed convection in an horizontal channel flow: DNS and assessment of RANS turbulence models
    De Santis, Dante
    De Santis, Andrea
    Shams, Afaque
    Kwiatkowski, Tomasz
    [J]. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2018, 127 : 345 - 358
  • [7] A robust and accurate outflow boundary condition for incompressible flow simulations on severely-truncated unbounded domains
    Dong, S.
    Karniadakis, G. E.
    Chryssostomidis, C.
    [J]. JOURNAL OF COMPUTATIONAL PHYSICS, 2014, 261 : 83 - 105
  • [9] Feasibility of full-core pin resolved CFD simulations of small modular reactor with momentum sources
    Fang, Jun
    Shaver, Dillon R.
    Tomboulides, Ananias
    Min, Misun
    Fischer, Paul
    Lan, Yu-Hsiang
    Rahaman, Ronald
    Romano, Paul
    Benhamadouche, Sofiane
    Hassan, Yassin A.
    Kraus, Adam
    Merzari, Elia
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2021, 378
  • [10] FENG B., 2021, DEV ADV REACTOR MODE