Thermo-economic and environmental analyses of supercritical carbon dioxide Brayton cycle for high temperature gas-cooled reactor

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yujia Zhou , Yifan Zhang , Hongzhi Li , Yu Yang , Wengang Bai , Chun Zhang , Xuwei Zhang , Mingyu Yao
{"title":"Thermo-economic and environmental analyses of supercritical carbon dioxide Brayton cycle for high temperature gas-cooled reactor","authors":"Yujia Zhou ,&nbsp;Yifan Zhang ,&nbsp;Hongzhi Li ,&nbsp;Yu Yang ,&nbsp;Wengang Bai ,&nbsp;Chun Zhang ,&nbsp;Xuwei Zhang ,&nbsp;Mingyu Yao","doi":"10.1016/j.pnucene.2024.105461","DOIUrl":null,"url":null,"abstract":"<div><div>The supercritical carbon dioxide (sCO<sub>2</sub>) Brayton cycle demonstrates special advantages for the high temperature gas-cooled reactor (HTGR) delivered into commercial operation recently in China, with its high efficiency, compactness, flexibility, and safety compared to the conventional steam Rankine cycle. However, the large temperature rise of 500 °C for the HTGR brings new challenges for the design of sCO<sub>2</sub> cycle. Here, we present the first study on the thermodynamic, economic, and environmental performance of the HTGR-sCO<sub>2</sub> system using the energy, exergy, economic, and environmental (4E) evaluation method. The cascaded sCO<sub>2</sub> cycle made up of two independent sCO<sub>2</sub> cycles is proposed, which are arranged in series on the cold side of reactor heat exchanger. We show that the cascaded sCO<sub>2</sub> cycle can utilize the heat absorption from HTGR effectively by optimizing the cycle configurations of top and bottom sub-cycles. The improved cascaded sCO<sub>2</sub> cycle minimizes the exergy loss, and increases the thermal efficiency to 43.2% when compared to the steam Rankine cycle of HTGR demonstration power plant and the single recompression cycle. By balancing the fixed-capital investment cost with the net power, the levelized cost of electricity can be reduced to 0.0283$/kWh. The life-cycle GHG emission intensity of HTGR-sCO<sub>2</sub> systems is about 6.5gCO<sub>2,eq</sub>/kWh, which is much smaller than that of coal-fired power plants, suggesting a great potential for decarbonization of the HTGR-sCO<sub>2</sub> system. Our study may find implications for the advancement of the sCO<sub>2</sub> Brayton cycle in next-generation nuclear power plant.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":3.3000,"publicationDate":"2024-09-27","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/S0149197024004116","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

The supercritical carbon dioxide (sCO2) Brayton cycle demonstrates special advantages for the high temperature gas-cooled reactor (HTGR) delivered into commercial operation recently in China, with its high efficiency, compactness, flexibility, and safety compared to the conventional steam Rankine cycle. However, the large temperature rise of 500 °C for the HTGR brings new challenges for the design of sCO2 cycle. Here, we present the first study on the thermodynamic, economic, and environmental performance of the HTGR-sCO2 system using the energy, exergy, economic, and environmental (4E) evaluation method. The cascaded sCO2 cycle made up of two independent sCO2 cycles is proposed, which are arranged in series on the cold side of reactor heat exchanger. We show that the cascaded sCO2 cycle can utilize the heat absorption from HTGR effectively by optimizing the cycle configurations of top and bottom sub-cycles. The improved cascaded sCO2 cycle minimizes the exergy loss, and increases the thermal efficiency to 43.2% when compared to the steam Rankine cycle of HTGR demonstration power plant and the single recompression cycle. By balancing the fixed-capital investment cost with the net power, the levelized cost of electricity can be reduced to 0.0283$/kWh. The life-cycle GHG emission intensity of HTGR-sCO2 systems is about 6.5gCO2,eq/kWh, which is much smaller than that of coal-fired power plants, suggesting a great potential for decarbonization of the HTGR-sCO2 system. Our study may find implications for the advancement of the sCO2 Brayton cycle in next-generation nuclear power plant.
用于高温气冷堆的超临界二氧化碳布雷顿循环的热经济和环境分析
与传统的蒸汽朗肯循环相比,超临界二氧化碳(sCO2)布雷顿循环具有高效、紧凑、灵活和安全等优点,适用于最近在中国投入商业运行的高温气冷堆(HTGR)。然而,高温气冷堆 500 ℃ 的大幅升温给 sCO2 循环的设计带来了新的挑战。在此,我们首次采用能量、放能、经济和环境(4E)评价方法对高温热电联产-sCO2 系统的热力学、经济和环境性能进行了研究。我们提出了由两个独立的 sCO2 循环组成的级联 sCO2 循环,它们串联布置在反应堆热交换器的冷侧。我们的研究表明,通过优化顶部和底部子循环的循环配置,级联 sCO2 循环可有效利用高温热电联产反应堆的吸热。与 HTGR 示范电站的蒸汽朗肯循环和单一再压缩循环相比,改进后的级联 sCO2 循环最大程度地减少了放能损失,并将热效率提高到 43.2%。通过平衡固定资本投资成本和净电量,平准化电力成本可降至 0.0283 美元/千瓦时。高温热电联供系统的生命周期温室气体排放强度约为 6.5gCO2,eq/kWh,远低于燃煤电厂,表明高温热电联供系统的脱碳潜力巨大。我们的研究可能会对下一代核电厂中二氧化碳布赖顿循环的发展产生影响。
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:481959085
Book学术官方微信