Enhancing Thermal-Hydraulic Performance in Nuclear Reactor Subchannels with Al2O3 Nanofluids: A CFD Analysis

被引:0
作者
Sardar, Mohammad A. I. [1 ]
Rahman, Mushfiqur [1 ]
Rubini, Philip [1 ]
机构
[1] Univ Hull, Sch Engn, Kingston Upon Hull HU6 7RX, England
关键词
nanofluid; base fluid; ANSYS; numerical analysis; heat transfer; Al2O3; Reynolds number; Nusselt number; pressurized water reactor; heat transfer coefficient; HEAT-TRANSFER ENHANCEMENT; PRESSURIZED-WATER REACTOR; CONDUCTIVITY; FLOW; MECHANISMS; TUBE;
D O I
10.3390/en17215486
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
In this paper, the performance of aluminum-based nanofluids with a possible application in pressurized water reactors is numerically investigated. A 605 mm long 4-rod array square (2 x 2) subchannel geometry with a uniform heat flux of 50 kW/m(2) has been used in CFD simulation. This analysis has been carried out using the RNG k-epsilon turbulence model with standard wall function in ANSYS FLUENT 2022R1. The impact of various flow conditions and nanofluid concentrations has been examined. The effects of variable velocities on nanofluid performance have been studied using different Reynolds numbers of 20,000, 40,000, 60,000, and 80,000. The analysis was conducted with Al2O3/water nanofluid concentrations of 1%, 2%, 3%, and 4%. A comparison of the Nusselt number based on five different correlations was conducted, and deviations from each correlation were then presented. The homogeneous single-phase mixer approach has been adopted to model nanofluid characteristics. The result shows a gradual enhancement in the heat transfer coefficient with increasing volume concentrations and Reynolds numbers. A maximum heat transfer coefficient has been calculated for nanofluid at maximum volume concentrations (phi = 4%) and highest velocities (Re = 80,000). Compared to the base fluid, heat transfer was enhanced by a factor of 1.09 using 4% Al2O3. The Nusselt number was calculated with a minimal error of 3.62% when compared to the Presser correlation and the maximum deviation has been found from the Dittus-Boelter correlation (13.77%). Overall, the findings suggest that aluminum-based nanofluids could offer enhanced heat transfer capabilities in pressurized water reactors.
引用
收藏
页数:22
相关论文
共 50 条
[41]   Numerical study of turbulent forced convection flow of nanofluids in a long horizontal duct considering variable properties [J].
Rostamani, M. ;
Hosseinizadeh, S. F. ;
Gorji, M. ;
Khodadadi, J. M. .
INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, 2010, 37 (10) :1426-1431
[42]   Numerical study of evaporation assisted hybrid cooling for thermal powerplant application [J].
Saha, Sudipta ;
Khan, Jamil ;
Farouk, Tanvir .
APPLIED THERMAL ENGINEERING, 2020, 166
[43]   A review on applications and challenges of nanofluids [J].
Saidur, R. ;
Leong, K. Y. ;
Mohammed, Hussein A. .
RENEWABLE & SUSTAINABLE ENERGY REVIEWS, 2011, 15 (03) :1646-1668
[44]   Heat Transfer Analysis of Nanofluid Based Coolant Used in the Sub-Channel of Fuel Assembly of a Pressurized Water Reactor [J].
Shojib, Sojibul Islam ;
Sardar, Mohammad Abdullah Imran ;
Joarder, Md. Sadman Anjum ;
Zakir, Md. Ghulam ;
Hossain, Altab .
JOURNAL OF NANOFLUIDS, 2023, 12 (02) :580-588
[45]   CFD study of heat transfer enhancement and fluid flow characteristics of laminar flow through tube with helical screw tape insert [J].
Tusar, Mehedi ;
Ahmed, Kazi ;
Bhuiya, Muhammad ;
Bhowmik, Palash ;
Rasul, Mohammad ;
Ashwath, Nanjappa .
2ND INTERNATIONAL CONFERENCE ON ENERGY AND POWER (ICEP2018), 2019, 160 :699-706
[46]   Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model [J].
Uzun, Sinem .
NUCLEAR TECHNOLOGY, 2025, 211 (04) :755-767
[47]   Aggregation structure and thermal conductivity of nanofluids [J].
Xuan, YM ;
Li, Q ;
Hu, WF .
AICHE JOURNAL, 2003, 49 (04) :1038-1043
[48]   Heat transfer enhancement of nanofluids [J].
Xuan, YM ;
Li, Q .
INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, 2000, 21 (01) :58-64
[49]   Application of CUPID for subchannel-scale thermal-hydraulic analysis of pressurized water reactor core under single-phase conditions [J].
Yoon, Seok Jong ;
Kim, Seul Been ;
Park, Goon Cherl ;
Yoon, Han Young ;
Cho, Hyoung Kyu .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (01) :54-67
[50]   Experimental investigation on flow boiling of HFE-7100 in a microchannel with pin fin array [J].
Zhuang, Xiaoru ;
Xie, Yichen ;
Li, Xiang ;
Yue, Sijun ;
Wang, Haitao ;
Wang, Handong ;
Yu, Peng .
APPLIED THERMAL ENGINEERING, 2023, 225