Analysis of the Alarm Generation and Display for the Reactor Accidents in HTR-PM

Chao Guo, Shuqiao Zhou, Duo Li, Xiaojin Huang
{"title":"Analysis of the Alarm Generation and Display for the Reactor Accidents in HTR-PM","authors":"Chao Guo, Shuqiao Zhou, Duo Li, Xiaojin Huang","doi":"10.1115/ICONE26-82483","DOIUrl":null,"url":null,"abstract":"Nuclear safety is one of the key issues for a nuclear power plant (NPP). The alarm system plays a critical role for the safe and efficient operation of an NPP which affects the correctness and efficiency of the operators in dealing with the accidents. It is even more important for the alarm system of a multi-modular NPP which has more than one reactor modules in a single unit because all the modules are usually monitored in the same main control room. The alarm generation and display mechanism of a typical multi-modular NPP, the High Temperature Gas-Cooled Reactor - Pebble bed Module (HTR-PM), is analyzed in this paper which has two reactor modules coupled to one steam turbine. Three operators are responsible for the operation of two nuclear islands and a conventional island, respectively. The alarm generation and display processes will be discussed in this paper. Firstly, the architecture of the RPS and the alarm system related to the red and yellow alarms is introduced. Then the generation and display mechanism of the red and yellow alarms is proposed. A protection variable of a design basis accident is given as an example for the alarm signal handling. The characteristics of the alarm system are then discussed. More optimization directions on the alarm design for multi-modular NPPs are proposed in the end.","PeriodicalId":65607,"journal":{"name":"International Journal of Plant Engineering and Management","volume":"13 1","pages":""},"PeriodicalIF":0.0000,"publicationDate":"2018-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"International Journal of Plant Engineering and Management","FirstCategoryId":"1089","ListUrlMain":"https://doi.org/10.1115/ICONE26-82483","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

Nuclear safety is one of the key issues for a nuclear power plant (NPP). The alarm system plays a critical role for the safe and efficient operation of an NPP which affects the correctness and efficiency of the operators in dealing with the accidents. It is even more important for the alarm system of a multi-modular NPP which has more than one reactor modules in a single unit because all the modules are usually monitored in the same main control room. The alarm generation and display mechanism of a typical multi-modular NPP, the High Temperature Gas-Cooled Reactor - Pebble bed Module (HTR-PM), is analyzed in this paper which has two reactor modules coupled to one steam turbine. Three operators are responsible for the operation of two nuclear islands and a conventional island, respectively. The alarm generation and display processes will be discussed in this paper. Firstly, the architecture of the RPS and the alarm system related to the red and yellow alarms is introduced. Then the generation and display mechanism of the red and yellow alarms is proposed. A protection variable of a design basis accident is given as an example for the alarm signal handling. The characteristics of the alarm system are then discussed. More optimization directions on the alarm design for multi-modular NPPs are proposed in the end.
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
HTR-PM反应堆事故报警产生与显示分析
核安全是核电厂的关键问题之一。报警系统对核电站的安全高效运行起着至关重要的作用,影响着操作人员处理事故的正确性和效率。对于一个多模块核电站的报警系统来说,这一点尤为重要,因为所有的模块通常都在同一个主控制室进行监控。本文分析了典型的多模块核电厂——高温气冷堆-球床模块(HTR-PM)的报警产生和显示机理。三家运营商分别负责两个核岛和一个常规岛的运营。本文将讨论报警的产生和显示过程。首先,介绍了RPS系统的结构以及与红黄报警相关的报警系统。然后提出了红色和黄色报警的产生和显示机制。以某设计基础事故的保护变量为例,对报警信号进行处理。然后讨论了报警系统的特点。最后提出了多模块核电站报警设计的优化方向。
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
自引率
0.00%
发文量
768
期刊最新文献
Preliminary LOCA Analysis of Heating-Reactor of Advanced Low-Pressurized and Passive Safety System (HAPPY) Estimation of Mitigation Effects of Sodium Nanofluid for SGTR Accidents in SFR Prediction and Sensibility Analysis for Nuclear Safety-Critical Software Reliability of DCS Numerical Study on the Two-Phase Flow for a Gas/Liquid Metal Magnetohydrodynamic Generator Simulated Training Instrument of Nuclear Radiation Reconnaissance Based on an Improved Ellipse Numerical Model
×
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