Numerical simulation study on the coupled heat transfer characteristics of liquid sodium and supercritical carbon dioxide

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Progress in Nuclear Energy Pub Date : 2026-05-01 Epub Date: 2026-02-13 DOI:10.1016/j.pnucene.2026.106293
Haonan Zhang , Zhengyu Gong , Songbai Cheng , Yanan Zhao
{"title":"Numerical simulation study on the coupled heat transfer characteristics of liquid sodium and supercritical carbon dioxide","authors":"Haonan Zhang ,&nbsp;Zhengyu Gong ,&nbsp;Songbai Cheng ,&nbsp;Yanan Zhao","doi":"10.1016/j.pnucene.2026.106293","DOIUrl":null,"url":null,"abstract":"<div><div>Among fourth-generation nuclear technology, the Sodium-cooled Fast Reactor (SFR) is one of the most mature reactors, offering high thermal efficiency and inherent safety advantages. The adoption of supercritical carbon dioxide (S-CO<sub>2</sub>) as the secondary-loop heat transfer medium in SFR has gained significant attention due to its potential to reduce heat exchanger size and improve thermal-to-electric conversion efficiency. Furthermore, the coupled system of an S-CO<sub>2</sub> Brayton cycle with an SFR effectively eliminates sodium-water reaction risks while achieving higher cycle efficiency compared to the steam Rankine cycle. Meanwhile, the Printed Circuit Heat Exchanger (PCHE), known for its compact structure and superior heat transfer performance, is considered as a promising candidate for thermal coupling between sodium and S-CO<sub>2</sub>. However, studies on heat transfer between sodium and S-CO<sub>2</sub> in PCHE remain scarce, and the associated technologies are still immature, necessitating further investigation into their thermal interaction and fundamental design guidelines. This study numerically investigates the heat transfer characteristics of liquid sodium and S-CO<sub>2</sub> through geometric modeling and simulation of a PCHE. Parameter-controlled simulations were performed to assess the impact of flow conditions and channel geometry on temperature and pressure distributions. The results indicate that temperature fields are primarily influenced by the inlet mass flow rates and temperatures of both fluids, while S-CO<sub>2</sub> outlet pressure, channel cross-section, and horizontal spacing show negligible effects (the variation in outlet temperature remains below 8 K). In contrast, pressure drop is mainly affected by the inlet mass flow rate of each fluid and the channel cross-sectional area, with an increase in channel diameter from 1.6 mm to 2.4 mm reducing the pressure drop by over 80%. The heat transfer coefficient is highly sensitive to changes in S-CO<sub>2</sub> mass flow rate and channel cross-sectional area; within the studied ranges, it increased by 58% and decreased by 44% respectively, both leading to significant performance variation. This study provides valuable insights for the design of sodium-S-CO<sub>2</sub> heat exchangers and supports the development of SFR technology.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"195 ","pages":"Article 106293"},"PeriodicalIF":3.2000,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197026000582","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2026/2/13 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

Among fourth-generation nuclear technology, the Sodium-cooled Fast Reactor (SFR) is one of the most mature reactors, offering high thermal efficiency and inherent safety advantages. The adoption of supercritical carbon dioxide (S-CO2) as the secondary-loop heat transfer medium in SFR has gained significant attention due to its potential to reduce heat exchanger size and improve thermal-to-electric conversion efficiency. Furthermore, the coupled system of an S-CO2 Brayton cycle with an SFR effectively eliminates sodium-water reaction risks while achieving higher cycle efficiency compared to the steam Rankine cycle. Meanwhile, the Printed Circuit Heat Exchanger (PCHE), known for its compact structure and superior heat transfer performance, is considered as a promising candidate for thermal coupling between sodium and S-CO2. However, studies on heat transfer between sodium and S-CO2 in PCHE remain scarce, and the associated technologies are still immature, necessitating further investigation into their thermal interaction and fundamental design guidelines. This study numerically investigates the heat transfer characteristics of liquid sodium and S-CO2 through geometric modeling and simulation of a PCHE. Parameter-controlled simulations were performed to assess the impact of flow conditions and channel geometry on temperature and pressure distributions. The results indicate that temperature fields are primarily influenced by the inlet mass flow rates and temperatures of both fluids, while S-CO2 outlet pressure, channel cross-section, and horizontal spacing show negligible effects (the variation in outlet temperature remains below 8 K). In contrast, pressure drop is mainly affected by the inlet mass flow rate of each fluid and the channel cross-sectional area, with an increase in channel diameter from 1.6 mm to 2.4 mm reducing the pressure drop by over 80%. The heat transfer coefficient is highly sensitive to changes in S-CO2 mass flow rate and channel cross-sectional area; within the studied ranges, it increased by 58% and decreased by 44% respectively, both leading to significant performance variation. This study provides valuable insights for the design of sodium-S-CO2 heat exchangers and supports the development of SFR technology.
液态钠与超临界二氧化碳耦合传热特性的数值模拟研究
在第四代核技术中,钠冷快堆(SFR)是最成熟的反应堆之一,具有高热效率和固有安全优势。超临界二氧化碳(S-CO2)作为SFR二回路传热介质,因其具有减小换热器尺寸和提高热电转换效率的潜力而受到广泛关注。此外,与蒸汽朗肯循环相比,S-CO2布雷顿循环与SFR的耦合系统有效地消除了钠-水反应风险,同时实现了更高的循环效率。同时,印刷电路热交换器(PCHE)以其紧凑的结构和优越的传热性能而被认为是钠与S-CO2之间热耦合的有前途的候选者。然而,关于PCHE中钠与S-CO2之间传热的研究仍然很少,相关技术仍然不成熟,需要进一步研究它们的热相互作用和基本设计准则。本文通过对PCHE的几何建模和模拟,对液态钠和S-CO2的传热特性进行了数值研究。进行了参数控制模拟,以评估流动条件和通道几何形状对温度和压力分布的影响。结果表明,温度场主要受进口质量、流量和两种流体温度的影响,而S-CO2出口压力、通道截面和水平间距的影响可以忽略不计(出口温度的变化保持在8 K以下)。压降主要受各流体进口质量流量和通道截面积的影响,通道直径从1.6 mm增加到2.4 mm,压降降低80%以上。换热系数对S-CO2质量流量和通道截面积的变化高度敏感;在研究范围内,它分别增加了58%和减少了44%,两者都导致了显著的性能变化。该研究为钠- s - co2换热器的设计提供了有价值的见解,并为SFR技术的发展提供了支持。
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
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
×
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:604180095
Book学术官方微信
小红书