Seismic modeling and simulation of the graphite core in gas-cooled micro-reactor

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Tianbao Lan , Xingming Peng , FengSheng , Wei Tan
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引用次数: 0

Abstract

To evaluate the structural safety of the graphite core in a gas-cooled micro-reactor and to assess its structural response under seismic loads, a study was conducted. By comparing the acceleration and velocity curves obtained from small-sized graphite block collision experiments and collision simulations, it was determined that the simulation results accurately represent the real collision behavior of graphite blocks. The collision stiffness and damping parameters were derived from these curves. Subsequently, simulations of graphite components in the core were performed to establish the stiffness and damping parameters of the graphite blocks, which were then incorporated into the core analysis calculations. To validate the accuracy of the core numerical model and simplify the vibration form, the core model was divided into in-plane and axial models. A full-core model calculation was then carried out to determine the forces between graphite components. The final results confirm that the graphite core adheres to the ASME design specifications under seismic loads.
气冷式微反应器中石墨芯的地震建模与模拟
为了评估气冷式微反应器中石墨核心的结构安全性,并评估其在地震荷载下的结构响应,进行了一项研究。通过比较从小型石墨块碰撞实验和碰撞模拟中获得的加速度和速度曲线,确定模拟结果准确地代表了石墨块的真实碰撞行为。根据这些曲线得出了碰撞刚度和阻尼参数。随后,对岩心中的石墨组件进行了模拟,以确定石墨块的刚度和阻尼参数,并将其纳入岩心分析计算。为了验证堆芯数值模型的准确性并简化振动形式,堆芯模型被分为平面内模型和轴向模型。然后进行了全岩心模型计算,以确定石墨组件之间的作用力。最终结果证实,在地震荷载作用下,石墨岩芯符合 ASME 设计规范。
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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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