An Effective Thermal Model of Coated Particle Dispersed Fuel with High Packing Fraction
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摘要: 准确预测核燃料的内部温度场分布，对于多层包覆颗粒弥散核燃料元件的设计及筛选具有重要的指导意义。在多层包覆颗粒及其弥散块体的等效热导率模型基础上，本文针对高体积份额情况分析建立了等效传热计算方法及其数值模型，并研究了燃料颗粒的空间分布、颗粒尺寸、团聚等因素对核燃料元件温度场的影响。本研究有助于理解多层包覆颗粒弥散核燃料元件的微观-宏观传热机制，为核燃料的设计、优化和安全分析提供了分析工具。Abstract: Accurate prediction of the temperature distribution in nuclear fuel is an important step for the design and screening of multi-coating particle dispersed nuclear fuel. This study aims to establish an effective thermal model and numerical solutions for macro scale heat transfer analysis by investigating the effective thermal properties of multi-coating particles and the dispersed fuel bulk. The effects of particle arrangement, sizes, clustering on temperature distribution inside nuclear fuel element was studied with the established effective model. This study helps clarify the micro- and macro- scale heat transfer mechanism of multi-coating particle dispersed fuel, and provides a guidance for the design, optimization and safety analysis of this type of fuel.
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Key words:
- Simulation /
- Dispersion fuel /
- Effective thermal conductivity
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表 1 热学分析中包覆颗粒各区域参数
Table 1. Regional Parameters of Coated Particle in Thermal Analysis
编号 材料 内径 外径 热导率 温度 1 核芯 a0 a1 k1 T1(r,Ф) 2 缓冲层 a1 a2 k2 T2(r,Ф) $ \vdots $ $ \vdots $ $ \vdots $ $ \vdots $ $ \vdots $ $ \vdots $ N+1 最外层涂层 aN aN+1 kN+1 TN+1(r,Ф) N+2 基体 — aN+2 kN+2 TN+2(r,Ф) “—”—不适用 
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表 2 验证计算所使用的热学输入条件
Table 2. Thermal Inputs for Verification Computation
参数名 参数值 初始温度/K 600 边界温度/K 600 燃料核芯功率密度/(W·mm−3) 3.315 包覆颗粒功率密度/(W·mm−3) 1.019 块体功率密度/(W·mm−3) 0.3078
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表 3 4种模型的预测温度扰动
Table 3. Predicted Temperature Rises of Four Models
模型 最高温度扰动/K 平均温度扰动/K 精细化模型 155.79 60.4 颗粒均匀化模型 123.92 57.18 单颗粒模型 46.21 1.67 块体均匀化模型 66.37 33.24 温度扰动为局部或平均温度减去边界温度
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表 4 随机模型的预测温度扰动
Table 4. Predicted Temerature Rises of Partcile Stochastic Models
模型 最高温度扰动/K 平均温度扰动/K 颗粒均匀化模型 123.92 57.18 随机模型1 128.14 50.70 随机模型2 126.28 50.61 随机模型3 132.23 50.19 平均值 128.9 50.5
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表 5 等间距模型与密排模型的温度扰动
Table 5. Temperature Rises of Equally Distributed Compact Arranged and Models
模型 最高温度扰动/K 平均温度扰动/K 密排模型 77.24 24.47 等间距模型 74.24 24.48
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[1] KONINGS R J M. Comprehensive nuclear materials[M]. Amsterdam: Elsevier, 2012 [2] SNEAD L L, TERRANI K A, VENNERI F, et al. Fully ceramic microencapsulated fuels: a transformational technology for present and next generation reactors-properties and fabrication of FCM fuel[J]. Transactions of the American Nuclear Society, 2011: 104. [3] TERRANI K A, SNEAD L L, GEHIN J C. Microencapsulated fuel technology for commercial light water and advanced reactor application[J]. Journal of Nuclear Materials, 2012, 427(1-3): 209-224. doi: 10.1016/j.jnucmat.2012.05.021 [4] LEE Y, CHO N Z. Three-dimensional single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized model[J]. Annals of Nuclear Energy, 2014(71): 254. doi: 10.1016/j.anucene.2014.03.039 [5] KNUDSON D L, MILLER G K, MILLER G K, et al. PARFUME theory and model basis report[R]. Idaho Falls: Idaho National Lab., 2009. [6] 刘振海,李文杰,陈平,等. FCM燃料热学性能分析[J]. 核动力工程,2016, 37(6): 150-154. [7] LIU M L, LEE Y, RAO D V. Development of effective thermal conductivity model for particle-type nuclear fuels randomly distributed in a matrix[J]. Journal of Nuclear Materials, 2018(508): 168-180. doi: 10.1016/j.jnucmat.2018.05.044 [8] SCHAPPEL D, TERRANI K, POWERS J J, et al. Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON[J]. Nuclear Engineering and Design, 2018(335): 116-127. doi: 10.1016/j.nucengdes.2018.05.018 [9] STAINSBY R, GRIEF A, WORSLEY M, et al. Investigation of local heat transfer phenomena in a pebble bed HTGR core: NR001/RP/002R01[R]. United Kingdom: Amec Foster Wheeler-Nuclear, 2009. [10] FOLSOM C P. Effective thermal conductivity of Tri-Isotropic (TRISO) fuel compacts[D]. Logan: Utah State University, 2012. [11] FOLSOM C, XING C H, JENSEN C, et al. Experimental measurement and numerical modeling of the effective thermal conductivity of TRISO fuel compacts[J]. Journal of Nuclear Materials, 2015(458): 198-205. doi: 10.1016/j.jnucmat.2014.12.042 [12] 曹芳成. 碳化硅基包覆型核燃料颗粒的氧化行为和热导性能研究[D]. 上海: 上海交通大学, 2018. [13] 刘子平, 周彪, 孙俊. 包覆颗粒燃料等效导热系数理论分析[C]//第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集. 惠州: 中国科学院近代物理研究所, 2019: 746-759. -
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