Dynamic Model of a Seawater Desalination Plant Based on the Nuclear Heating Reactor and MED-TVC

Yifei Pan, Z. Dong
{"title":"Dynamic Model of a Seawater Desalination Plant Based on the Nuclear Heating Reactor and MED-TVC","authors":"Yifei Pan, Z. Dong","doi":"10.1115/ICONE26-82556","DOIUrl":null,"url":null,"abstract":"The 200 MWth nuclear heat reactor II (NHR200-II) is a typical integral pressurized water reactor (iPWR) being developed by the institute of nuclear and new energy technology (INET) in Tsinghua university. The NHR200-II, which has inherent safety features such as full-range natural circulation, passive residual heat removal, self-pressurization and control rod hydraulically driving, can be adopted as a clean base-load energy source for a sea-water desalination plant having the process of multi-effect desalination with thermal vapor compression (MED-TVC). Dynamic modelling of the sea-water desalination plant coupled by the NHR200-II and MED-TVC is necessary for the design of its plant control strategy, which is important for the stable and efficient operation. In this paper, a lumped parameter dynamic model of NHR200II-based sea-water desalination plant with the process of MED-TVC is proposed based upon the conservation laws of mass, momentum and energy. The modeling verification in both the steady-state and open-loop dynamic-state are given, which show the suitability of applying this model for control system design. Finally, the closed-loop responses in the case of power-level maneuver from 100% to 50% full power is given.","PeriodicalId":65607,"journal":{"name":"International Journal of Plant Engineering and Management","volume":"6 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/ICONE26-82556","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 200 MWth nuclear heat reactor II (NHR200-II) is a typical integral pressurized water reactor (iPWR) being developed by the institute of nuclear and new energy technology (INET) in Tsinghua university. The NHR200-II, which has inherent safety features such as full-range natural circulation, passive residual heat removal, self-pressurization and control rod hydraulically driving, can be adopted as a clean base-load energy source for a sea-water desalination plant having the process of multi-effect desalination with thermal vapor compression (MED-TVC). Dynamic modelling of the sea-water desalination plant coupled by the NHR200-II and MED-TVC is necessary for the design of its plant control strategy, which is important for the stable and efficient operation. In this paper, a lumped parameter dynamic model of NHR200II-based sea-water desalination plant with the process of MED-TVC is proposed based upon the conservation laws of mass, momentum and energy. The modeling verification in both the steady-state and open-loop dynamic-state are given, which show the suitability of applying this model for control system design. Finally, the closed-loop responses in the case of power-level maneuver from 100% to 50% full power is given.
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
基于核加热堆和MED-TVC的海水淡化厂动态模型
200mth核电热堆II (NHR200-II)是清华大学核能与新能源技术研究所研制的典型整体式压水堆(iPWR)。NHR200-II具有全范围自然循环、被动余热排出、自增压、控制棒液压驱动等固有安全特性,可作为热蒸汽压缩多效脱盐海水淡化厂(MED-TVC)的清洁基负荷能源。NHR200-II与MED-TVC耦合的海水淡化厂动态建模是设计海水淡化厂控制策略的必要条件,对海水淡化厂稳定高效运行具有重要意义。本文基于质量、动量和能量守恒定律,建立了nhr200ii型海水淡化装置MED-TVC过程的集总参数动力学模型。在稳态和开环动态两种情况下对模型进行了验证,表明了将该模型应用于控制系统设计的适用性。最后给出了功率级机动从100%到50%全功率时的闭环响应。
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