Coolant Hydrodynamics in the PWR Reactor Core with TVS-Kvadrat of Various Designs

A. Dmitriev, A. L. Burov, T. D. Demkina, A. Dobrov, D. Doronkov, D. S. Doronkova, D. D. Kuritsin, A. Pronin, A. Ryazanov, D. Solntsev
{"title":"Coolant Hydrodynamics in the PWR Reactor Core with TVS-Kvadrat of Various Designs","authors":"A. Dmitriev, A. L. Burov, T. D. Demkina, A. Dobrov, D. Doronkov, D. S. Doronkova, D. D. Kuritsin, A. Pronin, A. Ryazanov, D. Solntsev","doi":"10.21122/2227-1031-2023-22-4-326-332","DOIUrl":null,"url":null,"abstract":". The paper presents the results of experimental studies of the hydrodynamics of the coolant in the core of the PWR reactor with fuel assemblies “TVS-Kvadrat” of various designs. Experimental studies of hydrodynamics consisted in studying the velocity fields and the process of cross-flow of coolant between adjacent fuel assemblies “TVS-Kvadrat” of various designs in homogeneous and mixed cores on large-scale experimental models, including fragments of two adjacent fuel assemblies “TVS-Kvadrat” and a gap between them. The test models differ in the number of installed grids, this is due to the fact that in a homogeneous core the hydraulic load along the height of the fuel assemblies is identical, and in a mixed core the hydraulic load is uneven due to the different number of installed grids. The hydrodynamics of the coolant has been studied on an aerodynamic open-loop based on the theory of hydrodynamic similarity, using individually calibrated pneumometric sensors. Based on the data obtained, the fields of local axial and transverse velocities in various sections along the length of the studied section of the test models have been constructed. The fields of local dimensionless transverse and axial flow velocities in the fuel bundles and the gap between the fuel assemblies “TVS-Kvadrat” of the PWR reactor core have been studied. Peculiarities of the process of transverse flow between adjacent “TVS-Kvadrat” of a homogeneous and the mixed core of the PWR reactor have been revealed. The results of experimental studies have been transferred to the developer of “TVS-Kvadrat”, that is  JSC “Experimental Design Bureau of Mechanical Engineering named after I. I. Afrikantov”,  for further use in justifying the design and operating modes of a nuclear power plant. ","PeriodicalId":297325,"journal":{"name":"Science & Technique","volume":"49 3 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2023-08-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Science & Technique","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.21122/2227-1031-2023-22-4-326-332","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

. The paper presents the results of experimental studies of the hydrodynamics of the coolant in the core of the PWR reactor with fuel assemblies “TVS-Kvadrat” of various designs. Experimental studies of hydrodynamics consisted in studying the velocity fields and the process of cross-flow of coolant between adjacent fuel assemblies “TVS-Kvadrat” of various designs in homogeneous and mixed cores on large-scale experimental models, including fragments of two adjacent fuel assemblies “TVS-Kvadrat” and a gap between them. The test models differ in the number of installed grids, this is due to the fact that in a homogeneous core the hydraulic load along the height of the fuel assemblies is identical, and in a mixed core the hydraulic load is uneven due to the different number of installed grids. The hydrodynamics of the coolant has been studied on an aerodynamic open-loop based on the theory of hydrodynamic similarity, using individually calibrated pneumometric sensors. Based on the data obtained, the fields of local axial and transverse velocities in various sections along the length of the studied section of the test models have been constructed. The fields of local dimensionless transverse and axial flow velocities in the fuel bundles and the gap between the fuel assemblies “TVS-Kvadrat” of the PWR reactor core have been studied. Peculiarities of the process of transverse flow between adjacent “TVS-Kvadrat” of a homogeneous and the mixed core of the PWR reactor have been revealed. The results of experimental studies have been transferred to the developer of “TVS-Kvadrat”, that is  JSC “Experimental Design Bureau of Mechanical Engineering named after I. I. Afrikantov”,  for further use in justifying the design and operating modes of a nuclear power plant. 
不同设计的TVS-Kvadrat压水堆堆芯冷却剂流体动力学
。本文介绍了采用不同设计的“TVS-Kvadrat”燃料组件对压水堆堆芯内冷却剂流体力学的实验研究结果。流体力学的实验研究是在大型实验模型上,研究了均匀堆芯和混合堆芯中不同设计的相邻燃料组件“TVS-Kvadrat”之间的速度场和冷却剂横流过程,包括两个相邻燃料组件“TVS-Kvadrat”的碎片和它们之间的间隙。试验模型在安装网格的数量上有所不同,这是由于在均匀堆芯中,沿燃料组件高度的水力载荷是相同的,而在混合堆芯中,由于安装网格的数量不同,水力载荷是不均匀的。基于流体动力学相似理论,利用单独标定的气动传感器,在气动开环上研究了冷却剂的流体动力学。根据实测数据,构建了试验模型各截面沿研究截面长度方向的局部轴向和横向速度场。研究了压水堆堆芯燃料束内局部无因次横流场和轴向流场以及燃料组件间隙场。揭示了压水堆均匀堆芯和混合堆芯相邻“TVS-Kvadrat”间横向流动过程的特点。实验研究的结果已转交给“TVS-Kvadrat”的开发商,即以阿夫里坎托夫命名的机械工程实验设计局JSC,以进一步用于证明核电站的设计和运行模式。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
自引率
0.00%
发文量
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信