Experimental Investigation of Control Rod Drops into Perturbed Fuel Assemblies

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
N. Park, O. Kwon, Y. Yoo, Tae-Suk Kim
{"title":"Experimental Investigation of Control Rod Drops into Perturbed Fuel Assemblies","authors":"N. Park, O. Kwon, Y. Yoo, Tae-Suk Kim","doi":"10.1115/1.4062275","DOIUrl":null,"url":null,"abstract":"\n This paper discusses permanent deformation of the fuel assembly of pressurized water reactors that can satisfy a drop time requirement of the control rod assembly. During a seismic event, the fuel assemblies and the reactor core exhibit transient vibration. When the fuel assemblies collide, they develop impact forces in the spacer grids along the fuel assemblies. If the impact forces on some spacer grids of the fuel assembly exceed an allowable strength, the buckling occurs in the corresponding spacer grids, followed by permanent deformation. The geometry change of the buckled spacer grids leads to the movement of the guide tube positions in the fuel assembly. Therefore the geometry change is associated with the distortion of the control rod drop path. In this study, the permanent deformation of the spacer grids was measured during the impact tests, and the maximum deviation of the guide tube from the original position was reviewed. Control rod drop tests were also performed to measure the change in drop time according to the deformation of the fuel assembly. Using actuators in the loop test facility, the authors realized the first and second bending mode shapes of the fuel assembly under the flowing water condition. Based on a series of drop tests, the critical fuel assembly deformation was identified that could lead to a violation of an allowable drop time of the control rod.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":null,"pages":null},"PeriodicalIF":0.5000,"publicationDate":"2023-04-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Engineering and Radiation Science","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/1.4062275","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

This paper discusses permanent deformation of the fuel assembly of pressurized water reactors that can satisfy a drop time requirement of the control rod assembly. During a seismic event, the fuel assemblies and the reactor core exhibit transient vibration. When the fuel assemblies collide, they develop impact forces in the spacer grids along the fuel assemblies. If the impact forces on some spacer grids of the fuel assembly exceed an allowable strength, the buckling occurs in the corresponding spacer grids, followed by permanent deformation. The geometry change of the buckled spacer grids leads to the movement of the guide tube positions in the fuel assembly. Therefore the geometry change is associated with the distortion of the control rod drop path. In this study, the permanent deformation of the spacer grids was measured during the impact tests, and the maximum deviation of the guide tube from the original position was reviewed. Control rod drop tests were also performed to measure the change in drop time according to the deformation of the fuel assembly. Using actuators in the loop test facility, the authors realized the first and second bending mode shapes of the fuel assembly under the flowing water condition. Based on a series of drop tests, the critical fuel assembly deformation was identified that could lead to a violation of an allowable drop time of the control rod.
控制棒滴入扰动燃料组件的实验研究
本文讨论了压水堆燃料组件的永久变形,以满足控制棒组件的下降时间要求。在地震事件中,燃料组件和反应堆堆芯表现出瞬态振动。当燃料组件碰撞时,它们在沿燃料组件的间隔网格中产生冲击力。如果对燃料组件的某些间隔网格的冲击力超过允许强度,则相应的间隔网格发生屈曲,随后发生永久性变形。屈曲间隔栅的几何变化导致导管在燃料组件中的位置的移动。因此,几何变化与控制棒跌落路径的畸变有关。在冲击试验中,测量了间隔栅的永久变形,并对导管与原始位置的最大偏差进行了审查。还进行了控制棒跌落试验,以根据燃料组件的变形测量跌落时间的变化。利用回路试验装置中的执行器,实现了燃油组件在流水工况下的一阶和二阶弯曲模态形状。基于一系列跌落试验,确定了可能导致控制棒超出允许跌落时间的燃料组件临界变形。
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
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
×
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