池沸腾下朝向SA508钢表面临界热流密度特性试验研究

田道贵, 胡啸, 陈炼, 常华健

田道贵, 胡啸, 陈炼, 常华健. 池沸腾下朝向SA508钢表面临界热流密度特性试验研究[J]. 原子能科学技术, 2020, 54(12): 2362-2368. DOI: 10.7538/yzk.2020.54.12.2362
引用本文: 田道贵, 胡啸, 陈炼, 常华健. 池沸腾下朝向SA508钢表面临界热流密度特性试验研究[J]. 原子能科学技术, 2020, 54(12): 2362-2368. DOI: 10.7538/yzk.2020.54.12.2362
TIAN Daogui, HU Xiao, CHEN Lian, CHANG Huajian. Experimental Research on Critical Heat Flux for Downward-facing Pool Boiling with SA508 Steel Plate[J]. Atomic Energy Science and Technology, 2020, 54(12): 2362-2368. DOI: 10.7538/yzk.2020.54.12.2362
Citation: TIAN Daogui, HU Xiao, CHEN Lian, CHANG Huajian. Experimental Research on Critical Heat Flux for Downward-facing Pool Boiling with SA508 Steel Plate[J]. Atomic Energy Science and Technology, 2020, 54(12): 2362-2368. DOI: 10.7538/yzk.2020.54.12.2362

池沸腾下朝向SA508钢表面临界热流密度特性试验研究

Experimental Research on Critical Heat Flux for Downward-facing Pool Boiling with SA508 Steel Plate

  • 摘要: 反应堆压力容器外部冷却(ERVC)是实现熔融物堆内滞留(IVR)的重要方案之一,而反应堆压力容器(RPV)外壁面的临界热流密度(CHF)决定了ERVC冷却能力的限值。为此建立小型CHF试验装置,并采用RPV用SA508钢制作试验块加热表面。以去离子水为试验工质,开展池沸腾下朝向CHF试验,研究真实RPV表面材料在不同倾角和过冷度条件下的CHF特性,及其老化效应对CHF的影响。结果表明:SA508钢表面极易氧化生锈,其CHF较不易生锈的铜和不锈钢表面要高;SA508钢表面CHF随倾角的增大而增加,但在30°附近存在转折,转折角以下范围内的CHF随倾角增加趋势不明显;CHF随过冷度的增加而增加,且基本呈线性变化。本试验有助于进一步认识RPV外壁面的CHF行为,为后续开展CHF增强方法研究奠定基础。

     

    Abstract: The external reactor vessel cooling (ERVC) is one of the important methods to achieve the in-vessel retention (IVR), while the critical heat flux (CHF) on the outside wall of the reactor pressure vessel (RPV) decides the maximum heat removal capacity of ERVC. In present work, a small CHF test facility was established. The test surface was made of SA508 steel which was the same surface material of prototype RPV. The deionized water was used as coolant in downward-facing CHF test under pool boiling condition. The influence of the real RPV material surface at different inclination angles and sub-cooling conditions on the CHF characteristics was studied. The influence of aging on CHF was also studied. The results show that the SA508 steel surface is easily oxidized, so its CHF is higher than that of copper and stainless steel surfaces. The CHF of SA508 steel surface increases with inclination angle, but there is a turning point near 30° and the CHF below the turning angle has no obvious trend with the increase of inclination angle. The CHF increases with the sub-cooling, and it shows linear growth characteristics. The test results provide a further understanding of the CHF behavior on the RPV outside wall and lay the foundation for future research work on CHF enhancement methods.

     

  • [1] ZHANG Y P, DENG K H, WANG C L, et al. Experimental investigation on saturated pool boiling CHF for downward facing heating surface with different sizes and aspect ratio[J]. International Journal of Thermal Sciences, 2019, 138: 459-466.
    [2] THEOFANOUS T G, ANGELINI S. Natural convection for invessel retention at prototypic Rayleigh numbers[J]. Nuclear Engineering and Design, 2000, 200: 1-9.
    [3] ROUGE S. SULTAN test facility for large-scale vessel coolability in natural convection at low pressure[J]. Nuclear Engineering and Design, 1997, 169: 185-195.
    [4] 陆维,胡腾,赵宇峰,等. 真实表面材料及其老化效应对反应堆压力容器ERVC-CHF影响的试验研究[J]. 原子能科学技术,2016,50(10):1782-1786.LU Wei, HU Teng, ZHAO Yufeng, et al. Experimental research on influence of real surface material and aging effect on ERVC-CHF of RPV[J]. Atomic Energy Science and Technology, 2016, 50(10): 1782-1786(in Chinese).
    [5] 张震,熊万玉,王雄,等. 严重事故条件下压力容器下封头外表面临界热流密度实验研究[J]. 核动力工程,2016,37(5):4-9.ZHANG Zhen, XIONG Wanyu, WANG Xiong, et al. Experimental research of critical heat flux on pressure vessel lower head external surface under severe accident[J]. Nuclear Power Engineering, 2016, 37(5): 4-9(in Chinese).
    [6] CHANG H J, HU T, LU W, et al. Experimental study on CHF using a full scale 2-D curved test section with additives and SA508 heater for IVR-ERVC strategy[J]. Experimental Thermal and Fluid Science, 2017, 84: 1-9.
    [7] KAM D H, CHOI Y J, JEONG Y H. Critical heat flux on downward-facing carbon steel flat plates under atmospheric condition[J]. Experimental Thermal and Fluid Science, 2018, 90: 22-27.
    [8] MEI Y, SHAO Y Q, GONG S J, et al. Effects of surface orientation and heater material on heat transfer coefficient and critical heat flux of nucleate boiling[J]. International Journal of Heat and Mass Transfer, 2018, 121: 632-640.
    [9] ZHONG D W, SUN J, MENG J A, et al. Effects of orientation and structure geometry on boiling heat transfer for downward facing IGTAC surfaces[J]. International Journal of Heat and Mass Transfer, 2018, 123: 468-472.
    [10] 毕景良,黄彦平,徐建军,等. 纳米流体饱和池沸腾传热及CHF模型研究[J]. 原子能科学技术,2017,51(6):1008-1015.BI Jingliang, HUANG Yanping, XU Jianjun, et al. Study of nanofluid saturated pool boiling heat ttansfer and CHF model[J]. Atomic Energy Science and Technology, 2017, 51(6): 1008-1015(in Chinese).
    [11] 陈红宇,杜军毅,邓林涛,等. 核反应堆压力容器锻件用SA508系列钢的比较和分析[J]. 大型铸锻件,2008(1):1-3.CHEN Hongyu, DU Junyi, DENG Lintao, et al. The comparison and analysis of SA508 series steel used for nuclear reactor pressure vessel forgings[J]. Heavy Casting and Forging, 2008(1): 1-3(in Chinese).
    [12] SOHAG F A, BECK F R, MOHANTA L, et al. Effects of subcooling on downward facing boiling heat transfer with micro-porous coating formed by cold spray technique[J]. International Journal of Heat and Mass Transfer, 2017, 106: 767-780.
    [13] 田道贵,孙立成,阎昌琪,等. 两相流动中摇摆引起的附加作用分析[J]. 核动力工程,2013,34(6):75-79.TIAN Daogui, SUN Licheng, YAN Changqi, et al. Analysis of rolling induced additional effect on two-phase flow[J]. Nuclear Power Engineering, 2013, 34(6): 75-79(in Chinese).
    [14] TIAN D G, YAN C Q, SUN L C. Evaluation of interfacial area transport equation in vertical bubbly two-phase flow in large diameter pipes[J]. Annals of Nuclear Energy, 2015, 75: 199-209.
    [15] WANG K, ERKAN N, GONG H, et al. Effects of carbon steel surface oxidation on critical heat flux in downward-face pool boiling[J]. International Journal of Heat and Mass Transfer, 2019, 136: 470-485.
    [16] THEOFANOUS T G, DINH T N, TU J P, et al. The boiling crisis phenomenon, Part Ⅱ: Dryout dynamics and burnout[J]. Experimental Thermal and Fluid Science, 2002, 26(6-7): 793-810.
    [17] LEE J, CHANG S H. An experimental study on CHF in pool boiling system with SA508 test heater under atmospheric pressure[J]. Nuclear Engineering and Design, 2012, 250: 720-724.
  • 期刊类型引用(2)

    1. 钟达文,廉学新,史昊鹏,韩昱程. 老化效应对涂层表面池沸腾传热性能的影响. 原子能科学技术. 2024(01): 93-102 . 本站查看
    2. 王建,张莉,矫明,刘厚励,费晓明. 氧化和工质中添加剂对SA508钢CHF影响的实验研究. 原子能科学技术. 2022(08): 1662-1670 . 本站查看

    其他类型引用(2)

计量
  • 文章访问数:  529
  • HTML全文浏览量:  0
  • PDF下载量:  845
  • 被引次数: 4
出版历程
  • 刊出日期:  2020-12-19

目录

    /

    返回文章
    返回