Experimental study on the pressure drop of helium purge gas in particle crushing pebble beds

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-08-15 DOI:10.1016/j.fusengdes.2024.114631
Hao Cheng , Zheng Fang , Bing Zhou , Baoping Gong , Shanshan Bu , Zhenzhong Li , Deqi Chen
{"title":"Experimental study on the pressure drop of helium purge gas in particle crushing pebble beds","authors":"Hao Cheng ,&nbsp;Zheng Fang ,&nbsp;Bing Zhou ,&nbsp;Baoping Gong ,&nbsp;Shanshan Bu ,&nbsp;Zhenzhong Li ,&nbsp;Deqi Chen","doi":"10.1016/j.fusengdes.2024.114631","DOIUrl":null,"url":null,"abstract":"<div><p>The solid breeder blanket is a critical component in fusion reactor, where helium purge gas flows through the solid breeder pebble bed to carry out the tritium generated during the fusion process. The flow pressure drop of helium purge gas within the breeder pebble bed is a significant parameter affecting the design of the tritium extraction system. Previous studies have indicated that the helium flow in the breeder pebble bed conforms to the theory of porous media flow. However, due to potential pebble breakage during the plasma operation, the pressure drop characteristics of the helium flow in breeder pebble bed may change as the void structure changes. The objective of this study is to measure the variation in flow pressure drop of the breeder pebble bed under different pebble crushing conditions. The flow pressure drops of intact beds (Alumina, diameter 1-1.2 mm) and four groups with different pebble breakage rates (3%, 5%, 7%, 9%) are measured using the pebble bed pressure drop test facility. The following results are obtained through experimental research: (1) The Ergun equation, Foumeny equation, and Reichelt equation can all reasonably match the experimental results of intact pebble beds; (2) The pressure drop across the pebble bed increases with the increase in pebble breakage rate, reaching approximately 1.6 times that of the intact bed at a 9% breakage rate; (3) A correlation for predicting the pressure drop of the broken pebble bed is established by introducing the pebble breakage rate (<span><math><mi>η</mi></math></span>) into the Ergun equation, which can be used to determine the pressure drop variation within a conservative range of breakage rates.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"207 ","pages":"Article 114631"},"PeriodicalIF":1.9000,"publicationDate":"2024-08-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379624004824","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

The solid breeder blanket is a critical component in fusion reactor, where helium purge gas flows through the solid breeder pebble bed to carry out the tritium generated during the fusion process. The flow pressure drop of helium purge gas within the breeder pebble bed is a significant parameter affecting the design of the tritium extraction system. Previous studies have indicated that the helium flow in the breeder pebble bed conforms to the theory of porous media flow. However, due to potential pebble breakage during the plasma operation, the pressure drop characteristics of the helium flow in breeder pebble bed may change as the void structure changes. The objective of this study is to measure the variation in flow pressure drop of the breeder pebble bed under different pebble crushing conditions. The flow pressure drops of intact beds (Alumina, diameter 1-1.2 mm) and four groups with different pebble breakage rates (3%, 5%, 7%, 9%) are measured using the pebble bed pressure drop test facility. The following results are obtained through experimental research: (1) The Ergun equation, Foumeny equation, and Reichelt equation can all reasonably match the experimental results of intact pebble beds; (2) The pressure drop across the pebble bed increases with the increase in pebble breakage rate, reaching approximately 1.6 times that of the intact bed at a 9% breakage rate; (3) A correlation for predicting the pressure drop of the broken pebble bed is established by introducing the pebble breakage rate (η) into the Ergun equation, which can be used to determine the pressure drop variation within a conservative range of breakage rates.

查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
颗粒破碎卵石床中氦气吹扫气体压降的实验研究
固体增殖毯是聚变反应堆中的一个关键部件,氦净化气体流经固体增殖鹅卵石床,以提取聚变过程中产生的氚。氦净化气体在增殖体卵石床内的流动压降是影响氚提取系统设计的一个重要参数。以往的研究表明,氦气在增殖卵石床内的流动符合多孔介质流动理论。然而,由于在等离子体运行过程中卵石可能会破裂,氦气在增殖卵石床中的压降特性可能会随着空隙结构的变化而改变。本研究的目的是测量增殖卵石床在不同卵石破碎条件下的流动压降变化。使用卵石床压降试验设备测量了完整卵石床(氧化铝,直径 1-1.2 毫米)和四组不同卵石破碎率(3%、5%、7%、9%)的流动压降。实验研究得出了以下结果:(1)Ergun 方程、Foumeny 方程和 Reichelt 方程都能合理地匹配完整卵石床的实验结果;(2)随着卵石破碎率的增加,横跨卵石床的压降也随之增加,大约达到完整卵石床的 1.6 倍;(3)随着卵石破碎率的增加,横跨卵石床的压降也随之增加,大约达到完整卵石床的 1.6 倍。6 倍;(3) 通过将卵石破碎率 (η)引入 Ergun 方程,建立了预测破碎卵石床压降的相关性,可用于确定破碎率保守范围内的压降变化。
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 去求助
来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
期刊最新文献
Research and development on vanadium alloys for fusion breeder blanket application JET CODAS - the final status Study and analysis of the design considerations for controlling vertical plasma position in ADITYA-U tokamak Novel high temperature tritium blanket designs for confined spaces in spherical tokamak fusion reactors Installation, thermal curing, qualification testing of divertor and position control coils in ADITYA-U tokamak
×
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
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 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 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1