中国工程试验堆堆芯入口流量分配特性实验研究

眭曦, 王盛, 杨祖毛, 闫晓

眭曦, 王盛, 杨祖毛, 闫晓. 中国工程试验堆堆芯入口流量分配特性实验研究[J]. 原子能科学技术, 2020, 54(2): 257-263. DOI: 10.7538/yzk.2019.youxian.0105
引用本文: 眭曦, 王盛, 杨祖毛, 闫晓. 中国工程试验堆堆芯入口流量分配特性实验研究[J]. 原子能科学技术, 2020, 54(2): 257-263. DOI: 10.7538/yzk.2019.youxian.0105
SUI Xi, WANG Sheng, YANG Zumao, YAN Xiao. Experimental Investigation of Flow Distribution Characteristic at Core Inlet in CENTER[J]. Atomic Energy Science and Technology, 2020, 54(2): 257-263. DOI: 10.7538/yzk.2019.youxian.0105
Citation: SUI Xi, WANG Sheng, YANG Zumao, YAN Xiao. Experimental Investigation of Flow Distribution Characteristic at Core Inlet in CENTER[J]. Atomic Energy Science and Technology, 2020, 54(2): 257-263. DOI: 10.7538/yzk.2019.youxian.0105

中国工程试验堆堆芯入口流量分配特性实验研究

Experimental Investigation of Flow Distribution Characteristic at Core Inlet in CENTER

  • 摘要: 堆芯入口流量分配研究是新型反应堆设计过程中一项重要的工程验证实验,其结果能为反应堆的热工水力及安全分析提供数据支撑。本文针对中国工程试验堆(CENTER),采用缩比模型开展了堆芯入口流量分配特性实验研究,在不同工况下获得了模拟燃料组件、铍/铝组件、钴靶组件及控制棒导向管内的流量分配因子。实验结果表明:在本文研究的工况范围中,堆芯中大部分冷却剂流过模拟燃料组件,同类型模拟组件间的流量分配较均匀,最大流量相对偏差在±4%以内。实验入口总流量对流量分配特性几乎没有影响。

     

    Abstract: Flow distribution investigation at core inlet is an important engineering validation experiment during the design process of a new type nuclear reactor. It can provide experimental data for thermal-hydraulics and safety analysis of nuclear reactor. A flow distribution characteristic experimental investigation at core inlet in China Engineering Test Reactor (CENTER) was carried out based on a scaled-down model. Flow distribution factors under different working conditions among simulating fuel assembly, beryllium/aluminum assembly, and cobalt target assembly and control rod guide tube simulators were obtained. Experiment results show that under the working conditions in this paper, large amount of coolant flows through simulating fuel assembly and the flow distribution factors among the same kind assemblies are homogeneous, and the max relative deviation is within ±4%. The total inlet flow in the experiment has little influence on flow distribution characteristic.

     

  • [1] BERRINGER R T, BISHOP A A. Pressure drop, flow distribution and mixing studies for a model heterogeneous reactor vessel[C]∥Yakeen Atomic Electric Company Research and Development Program. USA: Yakeen Atomic Electric Company, 1959.
    [2] HESTERONI G. Use of hydraulic models in nuclear reactor design[R]. USA: Westinghouse Electric Corporation, 1965.
    [3] LEE K B, IM I Y, LEE B J, et al. YGN 3&4 reactor flow model test[R]. Korea: Korea Atomic Research Institute, 1991.
    [4] KIM K, EUH D J, CHU I C, et al. Experimental study of the APR+ reactor core flow and pressure distributions under 4-pump running conditions[J]. Nuclear Engineering and Design, 2013, 265: 3957-3966.
    [5] PURAGLIESI R, ZHOU L, ZERKAK O, et al. Steady-state CFD simulations of an EPR reactor pressure vessel: A validation study based on the JUKIETTE experiments[J]. Nuclear Engineering and Design, 2016, 300: 41-56.
    [6] VICTOR P, ANNALISA M. Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPRTM: CFD investigations and comparison with experimental results[J]. Nuclear Engineering and Design, 2011, 241: 1478-1485.
    [7] ROHDE U, HOHNE T, KLIEM S, et al. Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor: Validation of CFD codes[J]. Nuclear Engineering and Design, 2007, 237: 1639-1655.
    [8] 洪忠元,刘树林,局世孝,等. 秦山核电厂反应堆整体模型水力试验[J]. 核科学与工程,1989,9(4):319-327.HONG Zhongyuan, LIU Shulin, JU Shixiao, et al. The whole model hydraulic test of Qinshan Nuclear Power Pant reactor[J]. Chinese Journal of Nuclear Science and Engineering, 1989, 9(4): 319-327(in Chinese).
    [9] 杨来生,宗桂芳,胡俊. 秦山核电二期工程反应堆水力模拟实验研究[J]. 核动力工程,2003,24(增刊):208-211.YANG Laisheng, ZONG Guifang, HU Jun. Reactor hydraulic simulation test study of Qinshan Phase Ⅱ NPP project[J]. Nuclear Power Engineering, 2003, 24(Suppl.): 208-211(in Chinese).
    [10] 张曙明,李华奇,赵民富,等. 秦山核电站二期反应堆堆芯流量分配数值分析[J]. 核科学与工程,2010,30(4):299-307.ZHANG Shuming, LI Huaqi, ZHAO Minfu, et al. Numerical analysis of flow distribution at the reactor core inlet of Qinshan Phase Ⅱ reactor[J]. Chinese Journal of Nuclear Science and Engineering, 2010, 30(4): 299-307(in Chinese).
    [11] 王盛,杨来生,方颖,等. CNP1000反应堆旁漏流、流量分配及交混特性研究[M]∥中国核动力研究设计院科学技术年报. 成都:中国核动力研究设计院,2009:11-13.
    [12] 喻丹萍,蒋贤国,张建伟,等. 中国先进研究堆全堆芯流致振动及流量分配试验研究[J]. 原子能科学技术,2008,42(增刊):711-714.YU Danping, JIANG Xianguo, ZHANG Jianwei, et al. Experiment study for flow-induced vibration and flow distribution on full scale core of China Advanced Research Reactor[J]. Atomic Energy Science and Technology, 2008, 42(Suppl.): 711-714(in Chinese).
    [13] 刘一哲,薛秀丽,许义军,等. 中国实验快堆全堆芯流量分配计算与试验[J]. 核动力工程,2012,33(增刊):100-103.LIU Yizhe, XUE Xiuli, XU Yijun, et al. Calculation and test of core flow rate distribution of China Experimental Fast Reactor[J]. Nuclear Power Engineering, 2012, 33(Suppl.): 100-103(in Chinese).
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  • 刊出日期:  2020-02-19

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