{"title":"Enhancing nuclear cogeneration efficiency using the low-grade waste heat recovery from nuclear hydrogen production system","authors":"Mehran Abolghasem , Khashayar Sadeghi , Seyed Hadi Ghazaie , Ekaterina Sokolova , Vitaly Sergeev , Naypak Ksenia , Wei Peng","doi":"10.1016/j.nucengdes.2025.114166","DOIUrl":null,"url":null,"abstract":"<div><div>This study investigates the integration of modular high-temperature steam electrolysis (HTSE) into a nuclear power plant (NPP) to enhance cogeneration efficiency through low-grade waste heat recovery. Three integration scenarios are proposed, focusing on changing the discharge points within the NPP second cycle to minimize the power loss factor (PLF) and maximize overall system efficiency. Using Aspen HYSYS, detailed simulations were conducted to evaluate the thermodynamic performance of each scenario, while a PLF-based economic model developed to calculate the levelized cost of hydrogen (LCOHY) in each scenario. The results demonstrate that discharging low-grade steam after the last high-pressure preheater (Scenario 3) yields the highest cogeneration efficiency (38%) and the lowest LCOHY at 1.74 $/kg for large-scale systems. This scenario also achieves a 36.7% reduction in heat cost compared to the baseline configuration, which shows the economic and technical superiority of this scenario. The study reveals that large-scale HTSE systems outperform small-scale configurations, with lower PLF (36%) and higher scalability. By integrating waste heat recovery and optimizing steam return points, this work provides a novel framework for improving nuclear-hydrogen cogeneration, contributing to sustainable energy systems and the global transition to net-zero emissions.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"441 ","pages":"Article 114166"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-19","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/S0029549325003437","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
This study investigates the integration of modular high-temperature steam electrolysis (HTSE) into a nuclear power plant (NPP) to enhance cogeneration efficiency through low-grade waste heat recovery. Three integration scenarios are proposed, focusing on changing the discharge points within the NPP second cycle to minimize the power loss factor (PLF) and maximize overall system efficiency. Using Aspen HYSYS, detailed simulations were conducted to evaluate the thermodynamic performance of each scenario, while a PLF-based economic model developed to calculate the levelized cost of hydrogen (LCOHY) in each scenario. The results demonstrate that discharging low-grade steam after the last high-pressure preheater (Scenario 3) yields the highest cogeneration efficiency (38%) and the lowest LCOHY at 1.74 $/kg for large-scale systems. This scenario also achieves a 36.7% reduction in heat cost compared to the baseline configuration, which shows the economic and technical superiority of this scenario. The study reveals that large-scale HTSE systems outperform small-scale configurations, with lower PLF (36%) and higher scalability. By integrating waste heat recovery and optimizing steam return points, this work provides a novel framework for improving nuclear-hydrogen cogeneration, contributing to sustainable energy systems and the global transition to net-zero emissions.
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.