Entropy generation analysis for fine flow states in PWR fuel assembly

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yunsheng Zhang , Guangliang Chen , Hao Qian , Lixuan Zhang , Jinchao Li , Hanqi Zhang , Dabin Sun , Hansheng Zhi
{"title":"Entropy generation analysis for fine flow states in PWR fuel assembly","authors":"Yunsheng Zhang ,&nbsp;Guangliang Chen ,&nbsp;Hao Qian ,&nbsp;Lixuan Zhang ,&nbsp;Jinchao Li ,&nbsp;Hanqi Zhang ,&nbsp;Dabin Sun ,&nbsp;Hansheng Zhi","doi":"10.1016/j.nucengdes.2024.113708","DOIUrl":null,"url":null,"abstract":"<div><div>Although the development of pressurized water reactor (PWR) technology has been relatively well developed so far, the depth of research on the thermo-hydraulic characteristics of the in-reactor coolant, especially the energy dissipation characteristics, still needs to be explored further. As an energy conversion system for PWR, entropy generation analysis plays a vital role in obtaining the irreversible loss of the coolant quantitatively and directionally, which is scarce. It is difficult to access the full coolant energy losses and thermal–hydraulic properties, and to provide direction and schemes for optimizing the flow field in the core. In this paper, the energy dissipation of the flow field is finely analyzed in the 5x5 rod bundle of the PWR core. For the irreversible dissipation of the flow energy of the coolant, the pulsation dissipation entropy generation and wall friction entropy generation account for about 90% and 10%, respectively, and the direct dissipation entropy generation is negligible. For the high dissipation region, the distribution of pulsation dissipation entropy generation in space has a directional role. The irreversibly dissipated energy is calculated using the definition of entropy generation, and the dissipation characteristics of cross-flow kinetic energy in different regions are analyzed accordingly. Lastly, the irreversible dissipation of temperature difference heat transfer is considered and correlated with the above hydraulic viscous dissipation, and the negative correlation characteristics of the two are found. Meanwhile, the parameter constructed by the two together has some advantage in flow field evaluation.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"430 ","pages":"Article 113708"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549324008082","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

Although the development of pressurized water reactor (PWR) technology has been relatively well developed so far, the depth of research on the thermo-hydraulic characteristics of the in-reactor coolant, especially the energy dissipation characteristics, still needs to be explored further. As an energy conversion system for PWR, entropy generation analysis plays a vital role in obtaining the irreversible loss of the coolant quantitatively and directionally, which is scarce. It is difficult to access the full coolant energy losses and thermal–hydraulic properties, and to provide direction and schemes for optimizing the flow field in the core. In this paper, the energy dissipation of the flow field is finely analyzed in the 5x5 rod bundle of the PWR core. For the irreversible dissipation of the flow energy of the coolant, the pulsation dissipation entropy generation and wall friction entropy generation account for about 90% and 10%, respectively, and the direct dissipation entropy generation is negligible. For the high dissipation region, the distribution of pulsation dissipation entropy generation in space has a directional role. The irreversibly dissipated energy is calculated using the definition of entropy generation, and the dissipation characteristics of cross-flow kinetic energy in different regions are analyzed accordingly. Lastly, the irreversible dissipation of temperature difference heat transfer is considered and correlated with the above hydraulic viscous dissipation, and the negative correlation characteristics of the two are found. Meanwhile, the parameter constructed by the two together has some advantage in flow field evaluation.
压水堆燃料组件中细微流动状态的熵生成分析
尽管压水堆(PWR)技术发展至今已相对成熟,但对堆内冷却剂热工水力特性,尤其是能量耗散特性的研究深度仍有待进一步探索。作为压水堆的能量转换系统,熵生成分析对定量、定向地获取冷却剂的不可逆损耗起着至关重要的作用,而这方面的研究却十分匮乏。要全面了解冷却剂的能量损失和热工水力特性,并为优化堆芯流场提供方向和方案十分困难。本文对压水堆堆芯 5x5 棒束流场的能量耗散进行了精细分析。对于冷却剂流动能量的不可逆耗散,脉动耗散熵生成和壁面摩擦熵生成分别约占 90% 和 10%,直接耗散熵生成可忽略不计。对于高耗散区域,脉动耗散熵的空间分布具有方向性。利用熵产生的定义计算不可逆耗散能量,并据此分析不同区域的横流动能耗散特征。最后,考虑了温差传热的不可逆耗散,并将其与上述水力粘性耗散相关联,发现了两者的负相关特性。同时,两者共同构建的参数在流场评价中具有一定的优势。
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
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
×
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