FLUID DYNAMICS IN THE CORE OF A WWER REACTOR WITH TVSA OF VARIOUS DESIGNS

S. Dmitriev, A. Dobrov, D. Doronkov, V. Lyskova, A. Pronin, E. Rubtsova, A. Ryazanov, D. Solntsev, A. Khrobostov
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Abstract

The results of experimental studies of the interassembly interaction of coolant in VVER reactor core which consists of TVSA-T and upgraded TVSA are presented. The modeling of coolant flow in the fuel assembly (FA) was carried out on an aerodynamic stand. The studies were carried out on a fragment model of VVER reactor core and consisted in measuring the velocity vector modulus in the characteristic zones of both TVSA and interassembly space of VVER reactor core. The measurements were carried out by a five-channel pneumometric probe. An analysis of the spatial distribution of projections of the absolute flow velocity allowed to detail the pattern of flow-round by the coolant flow of spacer, mixing and combined spacer grids TVSA. The results of study of interassembly interaction of coolant between neighboring TVSA-T and upgraded TVSA were adopted for practical use by JSC “Afrikantov OKBM” in assessing heat engineering reliability of VVER reactor cores and are included in the data-base for verification of computational fluid dynamics programs (CFD codes) and detailed cellular calculation of VVER reactor core.
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具有不同设计的真空管堆芯的流体动力学
本文介绍了由TVSA- t和升级版TVSA组成的VVER堆芯内冷却剂组装相互作用的实验研究结果。在气动台架上对燃油组件(FA)内的冷却剂流动进行了建模。研究是在VVER堆芯的碎片模型上进行的,包括在VVER堆芯的TVSA和组件间空间的特征区测量速度矢量模量。测量是由一个五通道气测探头进行的。通过对绝对流速投影的空间分布的分析,可以详细地描述由间隔、混合和组合间隔网格TVSA的冷却剂流动形成的流动模式。“Afrikantov OKBM”JSC在VVER堆芯热工程可靠性评估中采用了相邻TVSA- t和升级TVSA之间冷却剂组装相互作用的研究结果,并将其纳入计算流体动力学程序(CFD代码)验证数据库和VVER堆芯详细元胞计算数据库。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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