HPR1000核电机组外供汽工艺方案设计与分析

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-04-19 DOI:10.1016/j.nucengdes.2025.114084

Rongshun Xie , Shengguo Wu , Qiang Zeng , Jiajun Tang , Hui’er Sha , Gonghao Lu , Gang Hong , Yaoli Zhang

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引用次数: 0

摘要

随着全球对低碳能源需求的增加，核电在工业供热领域的应用受到了极大的关注。本文以华龙压水堆（HPR1000）为研究对象，通过对大型压水堆热电联产核电机组工业供汽系统的设计与优化，解决漳州古雷石化工业园的蒸汽需求。研究提出了四种供汽方案，并建立了相应的热力模型。结果表明，方案B（主汽/凝汽器）在燃料利用系数和供热能耗方面优于其他方案，分别达到48.87%和29.75%。此外，它对发电量的影响很小，仅减少12.02%。本研究的评价指标体系验证了HPR1000核电机组供应工业蒸汽的可行性。为机组能源的综合利用和经济效益的优化提供理论支持。

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Design and analysis of external steam supply process schemes for HPR1000 nuclear power units

With the global increase in demand for low-carbon energy, the application of nuclear power in the industrial heating field has received significant attention. This paper focuses on the Hua-long Pressurized Reactor (HPR1000), addressing the steam demand of the Gulei Petrochemical Industrial Park in Zhangzhou through the design and optimization of the industrial steam supply system for large PWR cogeneration nuclear power units. The study proposes four steam supply schemes and establishes corresponding thermal models. The results indicate that Scheme B (main steam/condenser) outperforms others regarding fuel utilization coefficient and heat supply power consumption, achieving 48.87% and 29.75%, respectively. Additionally, it has a minimal impact on electricity generation, reducing it by only 12.02%. This study’s evaluation indicator system verifies the feasibility of the HPR1000 nuclear power unit in supplying industrial steam. It provides theoretical support for the comprehensive utilization of the unit’s energy and the optimization of economic benefits.

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来源期刊

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.