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铅基反应堆燃料组件间隙横流周期性研究

范旭凯 彭天骥 范大军 朱彦雷 蔡义林 顾龙

范旭凯, 彭天骥, 范大军, 朱彦雷, 蔡义林, 顾龙. 铅基反应堆燃料组件间隙横流周期性研究[J]. 原子核物理评论, 2018, 35(2): 216-223. doi: 10.11804/NuclPhysRev.35.02.216
引用本文: 范旭凯, 彭天骥, 范大军, 朱彦雷, 蔡义林, 顾龙. 铅基反应堆燃料组件间隙横流周期性研究[J]. 原子核物理评论, 2018, 35(2): 216-223. doi: 10.11804/NuclPhysRev.35.02.216
FAN Xukai, PENG Tianji, FAN Dajun, ZHU Yanlei, CAI Yilin, GU Long. Study on Periodicity of Cross Flow in Gaps of a Lead-based Fast Reactor Fuel Assembly[J]. Nuclear Physics Review, 2018, 35(2): 216-223. doi: 10.11804/NuclPhysRev.35.02.216
Citation: FAN Xukai, PENG Tianji, FAN Dajun, ZHU Yanlei, CAI Yilin, GU Long. Study on Periodicity of Cross Flow in Gaps of a Lead-based Fast Reactor Fuel Assembly[J]. Nuclear Physics Review, 2018, 35(2): 216-223. doi: 10.11804/NuclPhysRev.35.02.216

铅基反应堆燃料组件间隙横流周期性研究

doi: 10.11804/NuclPhysRev.35.02.216
基金项目: 国家自然科学基金资助项目(11705255,11505258);中国科学院“西部之光”人才培养引进计划资助项目(29Y728010)
详细信息
    作者简介:

    范旭凯(1992-),男,山东滨州人,硕士,从事反应堆热工水力研究;E-mail:fanxk2016@impcas.ac.cn

    通讯作者: 顾龙,E-mail:gulong@impcas.ac.cn
  • 中图分类号: TL33

Study on Periodicity of Cross Flow in Gaps of a Lead-based Fast Reactor Fuel Assembly

Funds: National Natural Science Foundation of China(11705255, 11505258); CAS "Light of West China" Program (29Y728010)
  • 摘要: 燃料组件内冷却剂的横流对反应堆堆芯的换热有很大影响,为研究铅基反应堆燃料组件内冷却剂的横向速度分布,对CiADS反应堆燃料组件组件局部的7,19棒束的单螺距及多螺距多种几何进行建模和CFD(Computational Fluid Dynamics)模拟,并对其间隙内横向速度进行分析。研究表明: 19棒束组件内通道、角通道的相邻间隙内横向速度的分布在组件轴向和横向上有明显周期性,横向上根据两个内通道间隙平移旋转的位置关系由一个间隙的结果经过平移一定相位角度可以得到另一个间隙分布结果,沿轴向多螺距模型每个螺距长度内横向速度分布一致。7棒束组件在相同类型通道内横向速度分布大小及趋势与19棒束一致。少棒束单螺距组件结果进行横向及轴向的周期性延拓可以得到多棒束多螺距模型间隙内的横流分布。


    Cross flow of a coolant in fuel assembly had a great impact on the heat transfer of a reactor core. In order to study the characteristics of the cross flow in lead-based fast reactor assemblies, the CiADS fuel assemblies were used as research object. Fine geometric models and CFD simulation of 7 and 19 pin bundle and multi-pitch length assemblies based on CiADS fuel assemblies were carried out. The distribution of the cross flow velocity in several geometric models was compared and analyzed. The results show that the distribution of the cross flow velocity in gaps of interior and corner channel in 19 pin bundle has obvious periodicity in both axial and horizontal direction. In the horizontal direction, the results of one gap can be translated by a certain phase angle to obtain another gap distribution result according to the positional relationship of the translational rotations of the two internal channel gaps. The distribution of cross flow velocity is uniform in each pitch length of multi-pitch model in the axial direction. And the distribution of transverse flow in gaps of 7 pin bundle is similar to the distribution in the same kind of gaps in 19 pin bundle. The results of fewer pin bundle with single pitch length can be periodically extended in axial and transverse direction to obtain the characteristics of cross flow in geometric models with multi-pitch length and more rods.
  • [1] ZHANG Dalin, LIU Limin, LIU Minghao, et al. International Journal of Energy Research, 2018, 42:1834.
    [2] LV Kefeng. Study on the Thermal-hydraulic Behaviors of a Wire-wrapped Rod Bundle Cooled with Lead Bismuth Eutectic[D]. Heifei:University of Science and Technology of China, 2016. (in Chinese) (吕科锋. 液态铅铋合金在带统丝棒束组件内热工水力行为研究[D]. 合肥:中国科学技术大学, 2016.)
    [3] GAJAPATHY R, VELUSAMY K, SELVARAJ P, et al. Nuclear Engineering & Design, 2009, 239(11):2279.
    [4] MERZARI E, FISCHER P, YUAN H, et al. Nuclear Engineering & Design, 2016, 298:218.
    [5] ZHAO P, LIU J, GE Z, et al. Nuclear Engineering & Design, 2017, 317:146.
    [6] JEONG J H, SONG M S, LEE K L. Nuclear Engineering & Design, 2017, 313:470.
    [7] ROLFO S, PÉNIGUEL C, GUILLAUD M, et al. Nuclear Engineering & Design, 2012, 243:251.
    [8] RAZA W, KIM K Y. Nuclear Engineering & Design, 2008, 238(6):1332.
    [9] RAZA W, KIM K Y. Journal of Nuclear Science & Technology, 2008, 45(7):653.
    [10] CHEN J, ZHANG D, SONG P, et al. Annals of Nuclear Energy, 2018, 113:256.
    [11] LYU Kefeng, CHEN Liuli, YUE Chenchong, et al. Nuclear Power Engineering, 2015(6):27. (in Chinese) (吕科锋, 陈刘利, 岳晨冲, 等. 核动力工程, 2015(6):27.)
    [12] ZHOU Zhenwei. Numerical Study of Flow Behavior of Leadbismuth in Fuel Assembly with Wire Spacer[D]. Heifei:University of Science and Technology of China, 2014. (in Chinese) (周振慰. 含绕丝燃料组件内铅铋冷却剂流动特性的数值分析[D]. 合肥:中国科学技术大学, 2014.)
    [13] GE Zengfang, ZHOU Tao, BAI Yunqing, et al. Atomic Energy Science and Technology, 2015, 49(S1):167. (in Chinese) (葛增芳, 周涛, 柏云清, 等. 原子能科学技术, 2015, 49(S1):167.)
    [14] PENG Tianji, GU Long, WANG Dawei, et al. Atomic Energy Science and Technology, 2017, 51(12):2235. (in Chinese) (彭天骥, 顾龙, 王大伟, 等. 原子能科学技术, 2017, 51(12):2235.)
    [15] ZOU Y, ZHAO X, CHEN Q. Building Simulation, 2017, 11(1):1.
    [16] CHEN Fei. Numerical Study on the Flow and Heat Transfer Characteristics between Liquid Lead Bismuth Eutectic and Helium[D]. Beijing:University of Chinese Academy of Sciences, 2014. (in Chinese) (陈飞. 液态铅铋合金-氦气流动换热特性数值研究[D]. 北京:中国科学院大学, 2014.)
    [17] ANSYS Inc. ANSYS FLUENT 17.2 Theory Guide[M]. ANSYS Inc, Canonsburg, 2016.
    [18] CHEN S K, TODREAS N E, NGUYEN N T. Nuclear Engineering & Design, 2014, 267(2):109.
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出版历程
  • 收稿日期:  2018-03-02
  • 修回日期:  2018-04-04
  • 刊出日期:  2018-06-20

铅基反应堆燃料组件间隙横流周期性研究

doi: 10.11804/NuclPhysRev.35.02.216
    基金项目:  国家自然科学基金资助项目(11705255,11505258);中国科学院“西部之光”人才培养引进计划资助项目(29Y728010)
    作者简介:

    范旭凯(1992-),男,山东滨州人,硕士,从事反应堆热工水力研究;E-mail:fanxk2016@impcas.ac.cn

    通讯作者: 顾龙,E-mail:gulong@impcas.ac.cn
  • 中图分类号: TL33

摘要: 燃料组件内冷却剂的横流对反应堆堆芯的换热有很大影响,为研究铅基反应堆燃料组件内冷却剂的横向速度分布,对CiADS反应堆燃料组件组件局部的7,19棒束的单螺距及多螺距多种几何进行建模和CFD(Computational Fluid Dynamics)模拟,并对其间隙内横向速度进行分析。研究表明: 19棒束组件内通道、角通道的相邻间隙内横向速度的分布在组件轴向和横向上有明显周期性,横向上根据两个内通道间隙平移旋转的位置关系由一个间隙的结果经过平移一定相位角度可以得到另一个间隙分布结果,沿轴向多螺距模型每个螺距长度内横向速度分布一致。7棒束组件在相同类型通道内横向速度分布大小及趋势与19棒束一致。少棒束单螺距组件结果进行横向及轴向的周期性延拓可以得到多棒束多螺距模型间隙内的横流分布。


Cross flow of a coolant in fuel assembly had a great impact on the heat transfer of a reactor core. In order to study the characteristics of the cross flow in lead-based fast reactor assemblies, the CiADS fuel assemblies were used as research object. Fine geometric models and CFD simulation of 7 and 19 pin bundle and multi-pitch length assemblies based on CiADS fuel assemblies were carried out. The distribution of the cross flow velocity in several geometric models was compared and analyzed. The results show that the distribution of the cross flow velocity in gaps of interior and corner channel in 19 pin bundle has obvious periodicity in both axial and horizontal direction. In the horizontal direction, the results of one gap can be translated by a certain phase angle to obtain another gap distribution result according to the positional relationship of the translational rotations of the two internal channel gaps. The distribution of cross flow velocity is uniform in each pitch length of multi-pitch model in the axial direction. And the distribution of transverse flow in gaps of 7 pin bundle is similar to the distribution in the same kind of gaps in 19 pin bundle. The results of fewer pin bundle with single pitch length can be periodically extended in axial and transverse direction to obtain the characteristics of cross flow in geometric models with multi-pitch length and more rods.

English Abstract

范旭凯, 彭天骥, 范大军, 朱彦雷, 蔡义林, 顾龙. 铅基反应堆燃料组件间隙横流周期性研究[J]. 原子核物理评论, 2018, 35(2): 216-223. doi: 10.11804/NuclPhysRev.35.02.216
引用本文: 范旭凯, 彭天骥, 范大军, 朱彦雷, 蔡义林, 顾龙. 铅基反应堆燃料组件间隙横流周期性研究[J]. 原子核物理评论, 2018, 35(2): 216-223. doi: 10.11804/NuclPhysRev.35.02.216
FAN Xukai, PENG Tianji, FAN Dajun, ZHU Yanlei, CAI Yilin, GU Long. Study on Periodicity of Cross Flow in Gaps of a Lead-based Fast Reactor Fuel Assembly[J]. Nuclear Physics Review, 2018, 35(2): 216-223. doi: 10.11804/NuclPhysRev.35.02.216
Citation: FAN Xukai, PENG Tianji, FAN Dajun, ZHU Yanlei, CAI Yilin, GU Long. Study on Periodicity of Cross Flow in Gaps of a Lead-based Fast Reactor Fuel Assembly[J]. Nuclear Physics Review, 2018, 35(2): 216-223. doi: 10.11804/NuclPhysRev.35.02.216
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