Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM

IF 1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY
Bin Wu, Jinhua Wang, Yue Li, Haitao Wang, Tengyu Ma
{"title":"Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM","authors":"Bin Wu, Jinhua Wang, Yue Li, Haitao Wang, Tengyu Ma","doi":"10.1155/2022/1817191","DOIUrl":null,"url":null,"abstract":"The Chinese high-temperature gas-cooled reactor pebble-bed module, HTR-PM, began fuel loading in August 2021. The reactor refuels continuously, while the spent fuel is discharged from the core. The spent fuel conveying and loading system was designed to convey the spent fuel pebbles to the spent fuel building and load them into dry canisters for on-site interim storage. This study describes the operating principles of the main functions and introduces the experiments and commissioning tests of the system. Functional tests were carried out to indicate the items of mechanical and electrical equipment are functioning in accordance with the designed requirements. Experience learned from commissioning activities was also presented as feedback for future operation and design improvement.","PeriodicalId":21629,"journal":{"name":"Science and Technology of Nuclear Installations","volume":null,"pages":null},"PeriodicalIF":1.0000,"publicationDate":"2022-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"3","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Science and Technology of Nuclear Installations","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1155/2022/1817191","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 3

Abstract

The Chinese high-temperature gas-cooled reactor pebble-bed module, HTR-PM, began fuel loading in August 2021. The reactor refuels continuously, while the spent fuel is discharged from the core. The spent fuel conveying and loading system was designed to convey the spent fuel pebbles to the spent fuel building and load them into dry canisters for on-site interim storage. This study describes the operating principles of the main functions and introduces the experiments and commissioning tests of the system. Functional tests were carried out to indicate the items of mechanical and electrical equipment are functioning in accordance with the designed requirements. Experience learned from commissioning activities was also presented as feedback for future operation and design improvement.
HTR-PM乏燃料输送装载系统的设计、试验和调试
中国高温气冷堆卵石床模块HTR-PM于2021年8月开始装料。反应堆持续加油,乏燃料从堆芯排出。乏燃料输送和装载系统的设计目的是将乏燃料卵石输送到乏燃料建筑,并将其装载到干燥的罐中,用于现场临时储存。本文介绍了系统主要功能的工作原理,并介绍了系统的实验和调试测试。进行了功能测试,以表明机械和电气设备项目的功能符合设计要求。从调试活动中学到的经验也作为未来运行和设计改进的反馈。
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
Science and Technology of Nuclear Installations
Science and Technology of Nuclear Installations NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.30
自引率
9.10%
发文量
51
审稿时长
4-8 weeks
期刊介绍: Science and Technology of Nuclear Installations is an international scientific journal that aims to make available knowledge on issues related to the nuclear industry and to promote development in the area of nuclear sciences and technologies. The endeavor associated with the establishment and the growth of the journal is expected to lend support to the renaissance of nuclear technology in the world and especially in those countries where nuclear programs have not yet been developed.
×
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