NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070013(2025)
Research on efficient CFD calculation and analysis technology for sodium-cooled fast reactor core
Figures & Tables(17)
Fig. 2. Radial power factor distribution of the core (color online)
Fig. 3. Diagram of partition scheme for fuel assemblies (color online)
Fig. 4. Diagram of the geometry and grid of the IWF research model (color online)(a) Inter-wrapper and geometric model of fuel assemblies, (b) Grid division scheme
Fig. 6. Axial temperature contour of fuel assembly and IWF (color online)(a) y=0.1 m, (b) y=0.3 m, (c) y=0.5 m, (d) y=0.8 m
Fig. 7. Axial temperature distribution of fuel assembly and IWF (color online)
Fig. 8. Axial temperature contour of IWF (color online)(a) y=0.1 m, (b) y=0.3 m, (c) y=0.5 m, (d) y=0.8 m
Fig. 9. Axial temperature distribution in different zones (color online)
Fig. 10. Axial temperature distribution in different zones without flow dispensing (color online)
Fig. 11. Cross-sectional temperature contours at different heights (color online)(a) y=0.1 m, (b) y=0.3 m, (c) y=0.5 m, (d) y=0.8 m
Table 1. Dimensional parameters of the fuel assembly
View tableView in ArticleTable 1. Dimensional parameters of the fuel assembly
参数 Parameters 值 Value 燃料棒/组件 Fuel rod bundle/box 61 盒内对边距 Internal box edge to edge distance / mm 56.6 燃料组件盒厚度 Box wall thickness / mm 1.2 燃料组件盒间距 Box to box spacing / mm 2 堆芯高度 Core height / mm 456 上转换区高度 Height of upper axial conversion zone / mm 100 下转换区高度 Height of lower axial conversion zone / mm 250
Table 2. Working parameters of the CEFR core
View tableView in ArticleTable 2. Working parameters of the CEFR core
参数 Parameter 值 Value 热功率 Thermal power / MW 65 冷却剂流量 Sodium flow rate passing through the core / kg∙s-1 301 堆芯入口钠温度 Core inlet sodium temperature / ℃ 360 堆芯出口钠平均温度 Average temperature of sodium at the outlet of the core / ℃ 530
Table 3. Power and flow distribution of whole core assemblies
View tableView in ArticleTable 3. Power and flow distribution of whole core assemblies
组件名称 Name of assemblies 功率 Power / MW 功率占比 Power share / % 冷却剂流量Coolant flow rate / kg∙s-1 流量占比Flow rate share / % 燃料组件 Fuel assembly 61.958 95.32 264.42 95.32 控制棒组件 Control rod assembly 0.247 0.378 0.247 0.378 中子源组件 Neutron source assembly 0.059 0.091 0.059 0.091 第一反射层组件 The first reflection layer assembly 0.844 1.298 其他反射层组件 Other reflective layer assembly 1.106 1.7 0.844 1.298 屏蔽层组件 Shielding assembly 0.387 0.6 乏燃料组件 Spent fuel assembly 0.399 0.613 组件盒间流量 Flow rate between assembly boxes ― ― 1.106 1.7
Table 4. Power and flow rate in different zones
View tableView in ArticleTable 4. Power and flow rate in different zones
燃料组件分区 Flow partition code 分区组件数 Number of assembly boxes 最大组件功率 Maximum box power / kW 组件流量 Box flow rate / kg∙s-1 Ⅰ 15 969 3.9 Ⅱ 18 870 3.52 Ⅲ 21 791.5 3.18 Ⅳ 27 713.2 2.8
Table 5. Comparison of core pressure drop calculation results
View tableView in ArticleTable 5. Comparison of core pressure drop calculation results
堆芯压降 Core pressure drop 值 Value 验证值 Verification value / MPa 0.28 计算值 Calculated value / MPa 0.278 相对误差 Relative error 0.007 14
Table 6. Main parameters of porous media model
View tableView in ArticleTable 6. Main parameters of porous media model
参数 Parameter 值 Value 相对误差 Relative error 功率 Power / MW 62.124 0.27% 冷却剂流量 Sodium flow rate / kg∙s-1 264.22 0.08% 网格数量 Number of grids 194 400 计算时间 Computing time / s 14.757
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Yuchen SUN, Guangliang CHEN, Qiang ZHAO, Yizhi TIAN, Menglai LI. Research on efficient CFD calculation and analysis technology for sodium-cooled fast reactor core[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070013
Paper Information
Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering
Received: Jan. 2, 2025
Accepted: --
Published Online: Sep. 15, 2025
The Author Email: Guangliang CHEN (CHENGuangliang)
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