To investigate the effects of surface fouling on thermal-hydraulic performance of wire-wrapped fuel assemblies in lead-bismuth cooled reactors
a steady-state numerical model was developed for a 19-rod bundle with uniform lead oxide (PbO) deposits. Considering the fluid-solid conjugate heat transfer between lead-bismuth and fuel cladding
wire-wrapped and fouling layer
the effects of fouling layer thickness
lead-bismuth mass flow rate and total heating power on temperature and flow fields of the fuel assembly were analyzed. And then the distributions of lead-bismuth temperature and flow velocity in the assembly and the variation of fuel cladding wall temperature were obtained. Results show that PbO fouling layer with a thinner surface coverage(≤40 μm)has little effect on the overall heat transfer coefficient of the fuel assembly
but it will cause the cladding temperature to rise. Increasing fouling thickness produces uniform axial distribution of maximum circumferential temperature on the assembly cladding outer wall while inducing nonlinear circumferential variations across sections. After increasing lead-bismuth flow rate and reducing heating power
the maximum temperature rise of fouling cladding outer wall decreases. Meanwhile
the influence of boundary conditions on cladding temperature intensifies with increasing fouling thickness. Compared with the case where the surface is uniformly covered fouling layer
local blockage caused by fouling deposition and component shedding will lead to a sudden increase in the local temperature of the cladding
which should be avoided.
关键词
Keywords
references
ZRODNIKOVA V, TOSHINSKY G I, KOMLEV O G, et al. Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors[J]. Progress in Nuclear Energy, 2008, 50(2/3/4/5/6): 170-178.
PACIO J, DAUBNER M, FELLMOSER F, et al. Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers[J]. Nuclear Engineering and Design, 2016, 301: 111-127.
MARINARI R, DI PIAZZA I, TARANTINO M, et al. Experimental tests and post-test analysis of non-uniformly heated 19-pins fuel bundle cooled by heavy liquid metal[J]. Nuclear Engineering and Design, 2019, 343: 166-177.
CHAI Xiang, LIU Xiaojing, XIONG Jinbiao, et al. Numerical investigation of thermal-hydraulic behaviors in a LBE-cooled 19-pin wire-wrapped rod bundle[J]. Progress in Nuclear Energy, 2020, 119: 103044.
孙畅, 焦守华, 柴翔, 等. 基于CFD方法的铅铋冷却燃料棒束的热工水力特性分析[J]. 原子能科学技术, 2020, 54(8): 1386-1394.SUN Chang, JIAO Shouhua, CHAI Xiang, et al. Thermal hydraulic analysis of LBE-cooled rod bundle based on CFD method[J]. Atomic Energy Science and Technology, 2020, 54(8): 1386-1394.
GONG Xing, SHORT M P, AUGER T, et al. Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors[J]. Progress in Materials Science, 2022, 126: 100920.
马韦刚, 邓平, 曹宇, 等. 316和T91钢在液态铅铋合金中的腐蚀行为研究[J]. 科学技术创新, 2023(9): 49-53.MA Weigang, DENG Ping, CAO Yu, et al. Corrosion behavior of 316 and T91 steel in liquid lead-bismuth eutectic alloy[J]. Scientific and Technological Innovation, 2023(9): 49-53.
SUN Yulin, YUAN Ganfeng, WANG Da, et al. Study on the corrosion behavior of austenitic stainless 15-15Ti for nuclear fuel cladding in lead-bismuth eutectic alloy with oxygen control[J]. Journal of Physics: Conference Series, 2022, 2393(1): 012018.
祁睦然. 液态铅铋合金氧泵与氧传感器的研发与性能研究[D]. 北京: 华北电力大学, 2023.
肖卓楠, 卞博, 杨杰, 等. 超临界机组跨临界区域Fe系沉积动力学过程研究[J]. 动力工程学报, 2024, 44(7): 1010-1018.XIAO Zhuonan, BIAN Bo, YANG Jie, et al. Study on dynamics of Fe sedimentation in transcritical region of supercritical units[J]. Journal of Chinese Society of Power Engineering, 2024, 44(7): 1010-1018.
赵伟萍, 吕玉坤, 阎维平. 污秽颗粒在太阳能光伏组件表面的沉积机理及组件积灰特性数值模拟[J]. 动力工程学报, 2022, 42(4): 316-325, 340.ZHAO Weiping, LV Yukun, YAN Weiping. Deposition mechanism of dust particles on the solar PV module surfaces and simulation on dust accumulation characteristics[J]. Journal of Chinese Society of Power Engineering, 2022, 42(4): 316-325, 340.
LUZZI L, LORENZI S, PIZZOCRI D, et al. Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR[R]. [S.l.]: ENEA, 2014: 18-22.
ANISIMOVA N I, BORDOVSKY G A, BORDOVSKY V A, et al. Electrical and thermal properties of Bi2O3, PbO and mixed oxides of Bi2O3-PbO system[C]//Proceedings of the 2004 IEEE International Conference on Solid Dielectrics. Toulouse: IEEE, 2004: 141-142.
CHENG Xu, TAK N I. Investigation on turbulent heat transfer to lead-bismuth eutectic flows in circular tubes for nuclear applications[J]. Nuclear Engineering and Design, 2006, 236(4): 385-393.
林俊杰. 绕丝方向对燃料组件热工特性影响研究[D]. 北京: 华北电力大学, 2022.
黄睿, 孙毓博, 傅俊森, 等. 铅铋冷却带绕丝棒束内腐蚀产物沉积特性数值模拟研究[J]. 原子能科学技术, 2025, 59(3): 597-606.HUANG Rui, SUN Yubo, FU Junsen, et al. Numerical study of deposition characteristic of corrosion product in lead-bismuth cooled wire-wrapped rod bundle[J]. Atomic Energy Science and Technology, 2025, 59(3): 597-606.
PACIO J, DAUBNER M, FELLMOSER F, et al. Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE[J]. Nuclear Engineering and Design, 2018, 330: 225-240.
BOVATI O, HASSAN Y. Numerical study of the impact of blockages on the thermal-hydraulic performance of 19 and 61-pin wire-wrapped bundles with conjugate heat transfer using RANS[J]. Annals of Nuclear Energy, 2023, 194: 110122.
樊亦江, 余大利, 刘书勇, 等. 铅铋冷却燃料棒束堵流事故CFD模拟与分析[J]. 核安全, 2022, 21(6): 97-105.FAN Yijiang, YU Dali, LIU Shuyong, et al. CFD simulation and analysis of blockage accident in a lead-bismuth eutectic cooled fuel rod bundle[J]. Nuclear Safety, 2022, 21(6): 97-105.