新型热管反应堆堆芯热工安全分析

张文文, 王成龙, 田文喜, 秋穗正, 苏光辉, 赵小林, 刘汉刚

张文文, 王成龙, 田文喜, 秋穗正, 苏光辉, 赵小林, 刘汉刚. 新型热管反应堆堆芯热工安全分析[J]. 原子能科学技术, 2017, 51(5): 822-827. DOI: 10.7538/yzk.2017.51.05.0822
引用本文: 张文文, 王成龙, 田文喜, 秋穗正, 苏光辉, 赵小林, 刘汉刚. 新型热管反应堆堆芯热工安全分析[J]. 原子能科学技术, 2017, 51(5): 822-827. DOI: 10.7538/yzk.2017.51.05.0822
ZHANG Wen-wen, WANG Cheng-long, TIAN Wen-xi, QIU Sui-zheng, SU Guang-hui, ZHAO Xiao-lin, LIU Han-gang. Thermal Safety Analysis of New Type Heat Pipe Reactor Core[J]. Atomic Energy Science and Technology, 2017, 51(5): 822-827. DOI: 10.7538/yzk.2017.51.05.0822
Citation: ZHANG Wen-wen, WANG Cheng-long, TIAN Wen-xi, QIU Sui-zheng, SU Guang-hui, ZHAO Xiao-lin, LIU Han-gang. Thermal Safety Analysis of New Type Heat Pipe Reactor Core[J]. Atomic Energy Science and Technology, 2017, 51(5): 822-827. DOI: 10.7538/yzk.2017.51.05.0822

新型热管反应堆堆芯热工安全分析

Thermal Safety Analysis of New Type Heat Pipe Reactor Core

  • 摘要: 针对新型空间热管反应堆,采用商用CFD软件FLUENT对其堆芯进行了稳态热工安全分析。根据MCNP物理计算的堆芯功率分布,选取功率份额最高的相邻3个燃料元件作为分析对象,对控制转鼓7种不同转动角度下的正常工况以及单根热管失效的事故工况进行计算分析,得到最热通道各层材料的温度分布。采用二维热管分析程序计算得到蒸汽区的温度分布,并作为三维计算模型的温度边界。堆芯功率分布采用用户自定义程序UDF进行添加。计算结果表明,在额定功率4.0 MW水平下,在正常工况以及单根热管失效事故工况下,热管具有足够的传热能力将堆芯裂变热导出,同时,堆芯最热通道各层材料温度均低于安全限值,且具有较大的安全裕度,满足设计要求。

     

    Abstract: The steady thermal characteristics of the new space heat pipe reactor were analyzed by applying the commercial CFD software FLUENT. According to the power distribution of core obtained by MCNP code calculation and selecting the three adjacent fuel elements with the highest power to analyze, seven normal working conditions with different control drum angles and single heat pipe failure accident condition were calculated and analyzed. The temperature distribution of each layer of the hottest fuel-heat pipe element was obtained. The temperature distribution of steam zone was calculated by the two-dimensional heat pipe analysis program and used as the temperature boundary of the three-dimensional model. The power distribution was added to the fuel by the user defined function (UDF). The results show that the heat pipe has sufficient heat transfer capacity to remove the fission power under the designed value 4.0 MW. Meanwhile, the material temperature of each layer is lower than the safety limits and has large safety margins. The core design meets the requirements.

     

  • [1] 苏著亭,杨继材,柯国土. 空间核动力[M]. 上海:上海交通大学出版社,2016:13-19.
    [2] POSTON D I. The heatpipe-operated mars exploration reactor (HOMER)[C]∥Space Technology and Applications International Forum-2001. USA: AIP Publishing, 2001.
    [3] BRAGG-SITTON S M. Analysis of space reactor system components: Investigation through simulation and non-nuclear testing[M]. USA: University of Michigan, 2004.
    [4] EL-GENK M S, TOURNIER J M P. “SAIRS” Scalable AMTEC integrated reactor space power system[J]. Progress in Nuclear Energy, 2004, 45(1): 25-69.
    [5] BUSHMAN A, CARPENTER D M, ELLIS T S, et al. The martian surface reactor: An advanced nuclear power station for manned extraterrestrial exploration, MIT-NSATR-003[R]. Cambridge: [s. n.], 2004.
    [6] EL-GENK M S, TOURNIER J M. Conceptual design of HP-STMC space reactor power system for 110 kWe[C]∥AIP Conference Proceedings. USA: IOP Institute of Physics Publishing Ltd., 2004.
    [7] BESS J D. A basic LEGO reactor design for the provision of lunar surface power[C]∥Proceedings of ICAPP. [S. l.]: [s. n.], 2008.
    [8] 李华琪,江新标,陈立新,等. HP-STMCs空间堆热管运行参数计算[J]. 现代应用物理,2014,5(2):154-160.LI Huaqi, JIANG Xinbiao, CHEN Lixin, et al. Calculation of operating parameters for HP-STMCs space nuclear reactor heat pipes[J]. Modern Applied Physics, 2014, 5(2): 154-160(in Chinese).
    [9] 王成龙,宋健,陈静,等. TOPAZ-Ⅱ改进型热管辐射换热器传热单元数值研究[J]. 原子能科学技术,2016,50(1):80-85.WANG Chenglong, SONG Jian, CHEN Jing, et al. Numerical study of heat transfer unit on improved thermal-radiator of TOPAZ-Ⅱ[J].Atomic Energy Science and Technology, 2016, 50(1): 80-85(in Chinese).
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  • 刊出日期:  2017-05-19

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