螺旋十字燃料组件沸腾传热及燃料元件热力耦合特性研究

丛腾龙; 高勇; 程毅; 蔡孟珂; 张琦; 肖瑶; 刘茂龙; 顾汉洋

doi:10.13832/j.jnpe.2023.05.0216

螺旋十字燃料组件沸腾传热及燃料元件热力耦合特性研究

doi: 10.13832/j.jnpe.2023.05.0216

1.
上海交通大学核科学与工程学院，上海，200240
2.
中广核研究院有限公司，广东深圳，518000

基金项目: 上海市自然科学基金项目（23ZR1428300）；国家自然科学基金重点项目（12135008）；黑龙江省自然科学基金（YQ2020A003）

详细信息

作者简介:
丛腾龙（1988—），男，博士，副教授，现主要从事燃料组件设计和性能分析方面的研究，E-mail: tlcong@sjtu.edu.cn

中图分类号: TL334
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出版历程
- 收稿日期: 2023-06-07
- 修回日期: 2023-07-12
- 刊出日期: 2023-10-13

Numerical Study on Boiling Heat Transfer and Thermal-Mechanical Characteristics of Helical Cruciform Fuel Assembly

1.
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China
2.
China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, 518000, China

摘要

摘要: 螺旋十字燃料（HCF）组件是一种新型的燃料组件设计方案，相对于传统的圆棒或板状燃料，HCF组件具有强交混、自支撑、无格架的特点。为评价HCF组件在热工水力和力学方面的性能，本文基于流固共轭传热方法建立了HCF组件两相沸腾传热模型和燃料棒热力耦合分析模型，获得了两相条件下的燃料棒和冷却剂温度、冷却剂空泡份额等参数分布以及不同燃耗深度下的燃料棒应力分布。结果表明，相对于圆棒组件，HCF组件可降低燃料中心温度和表面平均热流密度；发生沸腾临界时，HCF组件的线功率密度高于传统圆棒组件。初步热力耦合分析发现，对于金属芯体无气隙的HCF元件，燃料棒在辐照条件下受到较大的应力。
- 螺旋十字燃料（HCF） /
- 沸腾传热 /
- 临界热流密度（CHF） /
- 交混 /
- 热力耦合 /
- 燃料性能
Abstract: The helical cruciform fuel (HCF) assembly is an innovative design for nuclear reactor fuel. Compared to the traditional cylinder or plate type fuel, the HCF assembly has the features of intensive mixing, self-support and no requirement of spacer grid. The two-phase conjugate heat transfer model for HCF assembly and the thermal-mechanical analysis model for HCF rod were built to evaluate the performances of HCF from the aspects of thermohydraulics and mechanics, respectively. The distributions of fuel rod and coolant temperature and coolant void fraction under two-phase conditions, and the fuel rod stress distribution under different burnup were obtained. The results show that the HCF assembly can reduce the fuel center temperature and the average surface heat flux compared with traditional circular rod fuel assembly. When boiling crisis was triggered, the linear heat flux of HCF assembly was higher than that of traditional fuel assembly. The preliminary thermal-mechanical analysis shows that the fuel rod is subject to great stress under irradiation for HCF elements with metal core without air gap.
- Helical cruciform fuel (HCF) /
- Boiling heat transfer /
- Critical heat flux (CHF) /
- Mixing /
- Thermal-mechanical /
- Fuel performance

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图 1 圆管内DNB型CHF预测值和实验值对比

Figure 1. Comparison between Calculated and Experimental DNB-type CHF Data in Tube

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图 2 LWL正六边形组件DNB和干涸型CHF验证

Figure 2. Validation Based on LWL CHF Data for DNB and Dryout from Orthohexagonal Fuel Assembly

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图 3 维斯康星大学2×2棒束DNB和干涸型CHF验证

Figure 3. Validation Based on CHF Data for DNB and Dryout from UW-Madison 2×2 Rods Fuel Assembly　　　　　　　

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图 4 HCF元件肿胀验证曲线图

Figure 4. Validation Curves of Swelling for HCF Element

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图 5 HCF组件共轭传热分析用网格划分策略

Figure 5. Meshing for Conjugate Heat Transfer Analysis of HCF Assembly

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图 6 不同高度平面温度分布云图

Figure 6. Temperature Dstribution at Different Heights

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图 7 空泡份额分布

Figure 7. Distribution of Void Fraction

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图 8 沸腾临界时壁面温度云图

Figure 8. Wall Temperature Distribution at Boiling Crisis

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图 9 HCF元件几何模型图

Figure 9. Geometric Sketch for HCF Element

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图 10 HCF元件网格划分图

Figure 10. Meshing for HCF Element

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图 11 HCF元件温度和热流密度分布云图

Figure 11. Temperature and Heat Flux Contours for HCF Element　　　　　　

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图 12 HCF包壳温度和热流密度分布曲线图

Figure 12. Temperature and HFL Curves for HCF Cladding

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图 13 HCF元件应力分布云图

Figure 13. Stress Distribution of HCF Element

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图 14 HCF包壳应力变化曲线图

Figure 14. Stress Curves for HCF Cladding

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参考文献(10)

[1]	PETROV Y V, ERYKALOV A N, ONEGIN M S. The fuel cycle of reactor PIK[C]//2002 International Meeting on Reduced Enrichment for Research and Test Reactors. Bariloche, Argentina: RAS, 2002: 1-11.
[2]	CONBOY T M. Assessment of helical-cruciform fuel rods for high power density LWRs[D]. Cambridge, MA: Massachusetts Institute of Technology, 2010.
[3]	MALONE J, TOTEMEIER A, SHAPIRO N, et al. Lightbridge corporation’s advanced metallic fuel for light water reactors[J]. Nuclear Technology, 2012, 180(3): 437-442. doi: 10.13182/NT12-A15354
[4]	ANSYS Inc.. ANSYS FLUENT theory guide[M]. Canonsburg, PA, USA: ANSYS Inc., 2011: 625-704.
[5]	IOILEV A, SAMIGULIN M, USTINENKO V, et al. Advances in the modeling of cladding heat transfer and critical heat flux in boiling water reactor fuel assemblies[C]. USA: The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12). Pittsburgh, Pennsylvania, 2007: 1-15.
[6]	KIM Y S, HOFMAN G L. AAA fuels handbook[M]. Argonne, Illinois, USA: Argonne National Laboratory, 2003: 26-30.
[7]	MIDDLEMAS S C, JANNEY D E. Current revision of the Metallic Fuels Handbook summarizing properties of fresh fuels[Z]. Idaho Falls, ID, United States: Idaho National Laboratory, 2020.
[8]	MACDONALD P E, THOMPSON L B. MATPRO: version 09. A handbook of materials properties for use in the analysis of light water reactor fuel rod behavior: TREE-NUREG-1005[R]. Idaho Falls, USA: Idaho National Laboratory, 1976.
[9]	DING S R, WANG Q M, HUO Y Z. Mechanical behaviors of the dispersion nuclear fuel plates induced by fuel particle swelling and thermal effect II: Effects of variations of the fuel particle diameters[J]. Journal of Nuclear Materials, 2010, 397(1-3): 80-91. doi: 10.1016/j.jnucmat.2009.12.012
[10]	HAGRMAN D L, REYMANN G A. MATPRO-Version 11: A handbook of materials properties for use in the analysis of light water reactor fuel rod behavior: NUREG/CR-0497[R]. Idaho Falls, ID, United States: Idaho National Laboratory, 1979.