Real-Time Temperature Field Recovery of a Heterogeneous Reactor Based on the Results of Calculations in a Homogeneous Core

V. S. Kuzevanov, S. K. Podgorny
{"title":"Real-Time Temperature Field Recovery of a Heterogeneous Reactor Based on the Results of Calculations in a Homogeneous Core","authors":"V. S. Kuzevanov, S. K. Podgorny","doi":"10.26583/npe.2022.1.05","DOIUrl":null,"url":null,"abstract":"Advanced pressurized water reactors are the main part of a new generation of nuclear power plant projects under development that provide cost-effective power production for various needs (Yemelyanov et al. 1982, Klimov 2002, Boyko et al. 2005, Baklushin 2011, Bays et al. 2019, Nuclear Technology Review 2019). The innovative technologies are aimed at improving the safety and reliability as well as at reducing the cost of NPPs. At the same time, improvements in design, technological and layout solutions are focused primarily on the reactor core. Assessments of the efficiency of these improvements are preceded by numerical simulations of the processes in the core, in particular heat generation and sink, with account for the difference between the study object and the standard version tested in operational practice.\n The authors of the article propose a method for calculating the temperature field in the core of a heterogeneous reactor (using the example of a pressurized water reactor), which makes it possible to quickly assess the level of temperature safety of various changes in the core and has the necessary speed for analyzing transients in real time.\n This method is based on the energy equation for an equivalent homogeneous core in the form of a heat equation that takes into account the main features of the simulated heterogeneous structure. The procedure for recovering the temperature field of a heterogeneous reactor uses the analytical relation obtained in this work for the heat sink function, taking into account inter-fuel element heat leakage losses.\n Calculations of temperature fields in the model of the PWR type reactor (The Westinghouse Pressurized Water Reactor Nuclear Plant 1984) were carried out in stationary and transient operating modes. The calculation results were compared with the results of CFD simulation. The area of competing use of the temperature field recovery method was indicated.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"10 1","pages":""},"PeriodicalIF":0.0000,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.26583/npe.2022.1.05","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"Energy","Score":null,"Total":0}
引用次数: 0

Abstract

Advanced pressurized water reactors are the main part of a new generation of nuclear power plant projects under development that provide cost-effective power production for various needs (Yemelyanov et al. 1982, Klimov 2002, Boyko et al. 2005, Baklushin 2011, Bays et al. 2019, Nuclear Technology Review 2019). The innovative technologies are aimed at improving the safety and reliability as well as at reducing the cost of NPPs. At the same time, improvements in design, technological and layout solutions are focused primarily on the reactor core. Assessments of the efficiency of these improvements are preceded by numerical simulations of the processes in the core, in particular heat generation and sink, with account for the difference between the study object and the standard version tested in operational practice. The authors of the article propose a method for calculating the temperature field in the core of a heterogeneous reactor (using the example of a pressurized water reactor), which makes it possible to quickly assess the level of temperature safety of various changes in the core and has the necessary speed for analyzing transients in real time. This method is based on the energy equation for an equivalent homogeneous core in the form of a heat equation that takes into account the main features of the simulated heterogeneous structure. The procedure for recovering the temperature field of a heterogeneous reactor uses the analytical relation obtained in this work for the heat sink function, taking into account inter-fuel element heat leakage losses. Calculations of temperature fields in the model of the PWR type reactor (The Westinghouse Pressurized Water Reactor Nuclear Plant 1984) were carried out in stationary and transient operating modes. The calculation results were compared with the results of CFD simulation. The area of competing use of the temperature field recovery method was indicated.
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
基于均质堆芯计算结果的非均质堆温度场实时恢复
先进压水堆是正在开发的新一代核电站项目的主要组成部分,为各种需求提供具有成本效益的电力生产(Yemelyanov等人,1982年,Klimov 2002年,Boyko等人,2005年,Baklushin 2011年,Bays等人,2019年,核技术评论2019年)。这些创新技术旨在提高核电站的安全性和可靠性,并降低其成本。与此同时,设计、技术和布局解决方案的改进主要集中在反应堆堆芯上。在评估这些改进的效率之前,先对堆芯中的过程进行数值模拟,特别是热的产生和冷却,考虑到研究对象与在操作实践中测试的标准版本之间的差异。本文作者提出了一种计算非均质堆堆芯温度场的方法(以压水堆为例),可以快速评估堆芯各种变化的温度安全水平,并具有实时分析瞬态的必要速度。该方法以等效均匀岩心的能量方程为基础,考虑了模拟非均质结构的主要特征,采用热方程的形式。在考虑燃料元件间热泄漏损失的情况下,恢复非均相反应堆温度场的程序使用了本工作中获得的热沉函数的解析关系。在固定和瞬态运行模式下,对压水堆模型(1984年西屋公司压水堆核电站)的温度场进行了计算。将计算结果与CFD模拟结果进行了比较。指出了温度场回收法的竞争应用领域。
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
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Energy-Nuclear Energy and Engineering
CiteScore
0.40
自引率
0.00%
发文量
30
期刊介绍: The scientific journal Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika is included in the Scopus database. Publisher country is RU. The main subject areas of published articles are Nuclear Energy and Engineering, Физика, Приборостроение, метрология и информационно-измерительные приборы и системы, Информатика, вычислительная техника и управление, Энергетика. Before sending a scientific article, we recommend you to read the section For authors. This will allow you to prepare an article better for publication, to make it more interesting for the readers and useful for the scientific community. By following these steps, you will greatly increase the likelihood of your scientific article publishing in journals included in international citation systems (e.g., Scopus). Then you may choose a different journal, select the journal included to list of SAC Russia journal list, or send your scientific work for review and publication.
期刊最新文献
Studies of the BN-350 Reactor Fuel, Structural and Absorbing Materials at the Hot Laboratory of the IPPE Study into the dependence of the Co-60 and Lu-177g efficiency production on the energy structure of neutron flux density On Dilation of the BN-350 Reactor Fuel Assemblies Reprocessing of Primary and Secondary Coolants During the BN-350 Reactor Decommissioning Principles of Construction and Development of an Automatic Protection System for Steam Generators of Fast Reactors
×
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