EXPERIMENTAL MODELING OF HEAT EXCHANGE IN HEAT GENERATING ASSEMBLIES OF FAST REACTORS IN ACCIDENT REGIMES UNDER NATURAL CONVECTION CONDITIONS

Yu. A. Kuzina, A. Sorokin, N. Denisova, M. Kascheev
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Abstract

The results of experimental studies of heat transfer carried out at the State Research Center RF - IPPE on models of fuel assemblies in cores and screens of fast reactors BOR-60, BN-350, BN-600, BN-800 (the relative pitch of the fuel element simulators varied in the range 1.04≤s/d≤1.24) with natural and mixed convection of liquid metal coolants, which are the basis for the development of design codes. Model fuel assemblies of fast reactors contain 37 fuel elements (fuel rod simulators) located in a triangular lattice and enclosed in a hexagonal cover. The elements were heated with nichrome heaters, which ensure a constant heat flux on the inner surface of the elements and along the length of the heat generation. The central, lateral and corner elements are rotary. On their surface, 12 chromel-alumel thermocouples each in covers made of X18H9T steel (diameter of the cover 0.8-0.5 mm, diameter of thermoelectrodes 0.2 mm) are embedded, measuring the coolant temperature in the collectors of the models, as well as in each cell at the exit from the bundles. The spacing of the elements is carried out using wire coils; variants of smooth fuel rod simulators are also used. Experimental studies on model fuel assemblies revealed regularities in the formation of temperature fields in fuel elements and coolant. Natural convection manifests itself in the region of low velocities, promotes fluid mixing between channels, leveling the uneven heating of the coolant in the cross section of the fuel assembly, and reduces the azimuthal non-uniformity of the temperature of the wall fuel elements in the fuel assembly. The results of experimental studies show that the effect of natural convection manifests itself in the range of Pe<10 (Re<2000) numbers in gratings with relative steps (s/d<1.05) and in wide bundles (s/d<1.3 to a greater extent in bundles of smooth fuel rods in comparison with bundles of ribbed fuel rods. The introduction of displacers into the peripheral channels of a fuel assembly does not fundamentally change the nature of the temperature field in a fuel assembly as compared to the version of the geometry of a fuel assembly without displacers. An attempt was made to generalize the experimental data using the Gr*Pr criterion, where Gr* is the modified Grashof number calculated from the local heat flux on the heat exchange surface and the axial coordinate measured from the beginning of heat generation. In the dependences DTwmax = f(Gr*Pr2) at Pe<100 or ribbed side elements and Pe<10 for smooth side elements, two regions of DTwmax change in the Gr*Pr2 growth function are observed - first, DTwmax ncreases to a certain “limiting” value characteristic for fixed Pe, and then - a drop in DTwmax at large values of the parameter Gr*Pr2. As the Peclet number increases, the “limiting” value of DTwmax hifts to the region of larger values of Gr*Pr2; and at Pe=370 or ribbed elements and Pe=26.5; 100 or smooth elements, the limiting value of DTwmax is not achieved in the investigated range of the Gr*Pr2 parameter variation. For smooth side elements, the limiting values of DTwmax are approximately the same for different Pe numbers and amount to DTwmax≈10.
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自然对流条件下事故状态下快堆产热组件热交换的实验模拟
在RF - IPPE国家研究中心对BOR-60、BN-350、BN-600、BN-800快堆堆芯和堆筛内燃料组件模型(燃料元件模拟器的相对节距在1.04≤s/d≤1.24范围内变化)在液态金属冷却剂自然对流和混合对流条件下的传热进行了实验研究,为设计规范的制定提供了依据。快堆燃料组件模型包含37个燃料元件(燃料棒模拟器),这些燃料元件位于三角形晶格中,并被封闭在六边形盖内。这些元素用镍铬合金加热器加热,这确保了元素的内表面和沿热量产生的长度有恒定的热流。中央,侧面和角落的元素是旋转的。在它们的表面上,嵌入了12个铬铝热电偶,每个热电偶都由X18H9T钢制成(覆盖直径0.8-0.5 mm,热电极直径0.2 mm),测量模型集热器中的冷却剂温度,以及在束出口的每个电池中。元件的间距使用线圈进行;各种光滑燃料棒模拟器也被使用。模型燃料组件的实验研究揭示了燃料元件和冷却剂温度场形成的规律。自然对流在低速区域表现出来,促进了通道间的流体混合,平整了燃料组件横截面冷却剂的不均匀加热,降低了燃料组件壁面燃料元件温度的方位不均匀性。实验研究结果表明,相对步长光栅(s/d<1.05)和宽束(s/d<1.3)中,自然对流的影响在Pe<10 (Re<2000)数范围内表现得更明显,光滑燃料棒束比肋状燃料棒束表现得更明显。在燃料组件的外围通道中引入置换器,与没有置换器的燃料组件的几何形状相比,不会从根本上改变燃料组件温度场的性质。尝试用Gr*Pr准则对实验数据进行推广,其中Gr*为根据换热表面局部热流密度和从产热开始测量的轴向坐标计算得到的修正Grashof数。在p <100或肋边单元和p <10时的依赖关系DTwmax = f(Gr*Pr2)中,Gr*Pr2生长函数的DTwmax变化有两个区域:首先,当p固定时,DTwmax增加到一定的“极限”值特征;然后,当参数Gr*Pr2较大时,DTwmax下降。随着Peclet数的增加,DTwmax的“极限”值移向Gr*Pr2值较大的区域;和在Pe=370或肋构件,Pe=26.5;在Gr*Pr2参数变化的研究范围内,没有达到DTwmax的极限值。对于光滑侧元,不同Pe数的DTwmax极限值近似相同,均为DTwmax≈10。
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