{"title":"Thermo-neutronic analysis of natural circulation in the ABV small modular reactor under ocean-induced motions","authors":"Sayed Abolhasan Nourashrafeddin, Mohsen Shayesteh","doi":"10.1016/j.nucengdes.2025.114525","DOIUrl":null,"url":null,"abstract":"<div><div>Floating deployment of Small Modular Reactors (SMRs) requires reliable passive cooling performance under dynamic ocean-induced motions. In this work, a comprehensive thermo-neutronic analysis of the ABV reactor was performed to assess the capability of its natural circulation system under inclination, heaving, and rolling conditions. A steady-state coupling between ANSYS CFX and PARCS was implemented, and transient CFD simulations were conducted for dynamic scenarios. Results show that at 30° inclination, the core mass flow decreases by about 9.7 % with a temperature rise of 3.3 K, while at 45° the reduction reaches 19.2 % and 6.9 K, accompanied by a slight decrease in <span><math><mrow><msub><mi>k</mi><mrow><mi>eff</mi></mrow></msub></mrow></math></span> and a shortened cycle length. Under heaving motion, coolant and power oscillations vary between ± 5 % and ± 18 % depending on amplitude and period. Rolling motion produces peripheral flow oscillations with amplitudes below ± 1.5 %, with limited effect on DNBR. These findings demonstrate that ocean-induced motions can significantly affect natural circulation, reactivity feedback, and safety margins, highlighting the necessity of coupled multi-physics modeling and the adoption of power derating and adaptive control strategies for floating nuclear power plants.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114525"},"PeriodicalIF":2.1000,"publicationDate":"2025-10-10","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/S0029549325007022","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
Floating deployment of Small Modular Reactors (SMRs) requires reliable passive cooling performance under dynamic ocean-induced motions. In this work, a comprehensive thermo-neutronic analysis of the ABV reactor was performed to assess the capability of its natural circulation system under inclination, heaving, and rolling conditions. A steady-state coupling between ANSYS CFX and PARCS was implemented, and transient CFD simulations were conducted for dynamic scenarios. Results show that at 30° inclination, the core mass flow decreases by about 9.7 % with a temperature rise of 3.3 K, while at 45° the reduction reaches 19.2 % and 6.9 K, accompanied by a slight decrease in and a shortened cycle length. Under heaving motion, coolant and power oscillations vary between ± 5 % and ± 18 % depending on amplitude and period. Rolling motion produces peripheral flow oscillations with amplitudes below ± 1.5 %, with limited effect on DNBR. These findings demonstrate that ocean-induced motions can significantly affect natural circulation, reactivity feedback, and safety margins, highlighting the necessity of coupled multi-physics modeling and the adoption of power derating and adaptive control strategies for floating nuclear power plants.
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.