Thermo-neutronic analysis of natural circulation in the ABV small modular reactor under ocean-induced motions

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Sayed Abolhasan Nourashrafeddin, Mohsen Shayesteh
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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 keff 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.
海洋运动下ABV小型模块化反应堆自然循环的热中子分析
浮动部署的小型模块化反应堆(smr)需要在动态海洋运动下可靠的被动冷却性能。在这项工作中,对ABV反应器进行了全面的热中子分析,以评估其自然循环系统在倾斜、起伏和滚动条件下的能力。实现了ANSYS CFX与PARCS之间的稳态耦合,并对动态场景进行了瞬态CFD仿真。结果表明:在岩心倾角为30°时,岩心质量流量下降了约9.7%,升温3.3 K,而在倾角为45°时,岩心质量流量下降了19.2%,升温6.9 K,同时keff略有下降,循环长度缩短。在起伏运动下,根据振幅和周期,冷却剂和功率振荡在±5%和±18%之间变化。滚动运动产生的周边流动振荡幅度小于±1.5%,对DNBR影响有限。这些研究结果表明,海洋运动可以显著影响自然循环、反应性反馈和安全裕度,突出了对浮动核电站进行耦合多物理场建模以及采用功率降准和自适应控制策略的必要性。
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来源期刊
Nuclear Engineering and Design
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.
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