SMR堆芯热工水力实验和代码验证与汽车旅馆测试设施

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Heikki Suikkanen , Joonas Telkkä , Antti Räsänen , Eetu Kotro , Michael Böttcher , Lucia Rueda-Villegas , Veronika Sunkova
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引用次数: 0

摘要

作为欧洲McSAFER研究项目的一部分,在模块化集成测试设备MOTEL上进行了热液压实验。该设施模拟了一个整体压力水小型模块化反应堆(SMR),带有一个螺旋蒸汽发生器和一个带有单独加热棒组的堆芯,其中功率可以单独控制。实验中施加了不同的非对称和环形径向堆芯功率分布,以引起浮力驱动冷却剂流动中的交叉流动。实验的目的是为计算流体动力学(CFD)和热工水力子通道代码的验证提供新的smr相关数据。实验结果表明,交叉流混合效应主要集中在堆芯顶部。在不同加热器区域之间获得流体温度测量的可见差异需要区域之间显着的功率梯度。使用ANSYS CFX进行CFD模拟,建立了包括整个设施主侧的详细模型,并使用换热器的独立模型进行了额外的研究。CFD模拟结果与实测结果吻合较好,进一步揭示了非对称加热情况下岩心流动特性的细节。此外,用CTF和VIPRE-01子信道码进行了仿真。CTF的模拟突出了该代码处理自然循环驱动的smr典型流量的能力,因为结果与实验吻合得很好,并且能够预测岩心不同区域的正确轴向温度分布。VIPRE-01溶液稳定性对流量、功率级和轴向节化高度敏感。由于收敛问题,使用VIPRE-01进行的模拟未成功结束,并且得出的结论是实验条件超出了代码当前的能力。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
SMR core thermal hydraulic experiments and code validation with the MOTEL test facility
Thermal hydraulic experiments with the modular integral test facility, MOTEL, were performed as a part of the European McSAFER research project. The facility models an integral pressure water small modular reactor (SMR) with a helical steam generator and a core with separate heater rod groups, in which power can be individually controlled. Different asymmetric and ring-shaped radial core power distributions were imposed in the experiments to provoke cross flows in the buoyancy-driven coolant flow. The purpose of the experiments was to produce new SMR-relevant data for the validation of computational fluid dynamic (CFD) and thermal-hydraulic subchannel codes. The experimental measurements revealed cross flow mixing effects, mainly in the top part of the core. Obtaining visible differences in the fluid temperature measurements between different heater regions required significant power gradients between the regions. CFD simulations were performed using ANSYS CFX with a detailed model comprising the whole primary side of the facility, and additional investigations were conducted with a stand-alone model of the heat exchanger. Good agreement with the measurements was obtained with the CFD simulations, which also revealed further details of the core flow characteristics in an asymmetric heating case. Furthermore, simulations with the subchannel codes, CTF and VIPRE-01, were performed. The simulations with CTF highlighted the code’s capability to handle flow rates typical to natural circulation driven SMRs, as the results agreed well with the experiments and were able to predict the correct axial temperature profiles in the different regions of the core. VIPRE-01 solution stability was found to be highly sensitive to the flow rate, the power level, and the axial nodalization. Simulations with VIPRE-01 ended unsuccessfully due to convergence issues, and it was concluded that the conditions of the experiments are beyond the current capabilities of the code.
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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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