{"title":"Numerical simulation study on the coupled heat transfer characteristics of liquid sodium and supercritical carbon dioxide","authors":"Haonan Zhang , Zhengyu Gong , Songbai Cheng , 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.
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.