Parametric reduced-order modeling of once-through steam generator via double proper orthogonal decomposition

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yifan Xu, Minjun Peng, Genglei Xia, Xiaobo Zeng
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引用次数: 0

Abstract

Mastering thermal–hydraulic characteristics of the once-through steam generator (OTSG) is essential for ensuring the stable operation and safety of reactors. While refined simulation models offer relatively accurate predictions for OTSG thermal–hydraulic research, the high computational cost often limits their applicability in system online- monitoring and real-time control. Specifically, the computational burden of these models can be prohibitive for multi-query simulation tasks such as optimization design and uncertainty analysis. Model order reduction (MOR) provides a solution that meets the need for both precision and speed in nuclear reactor system. Proper orthogonal decomposition (POD), as one of the representative MOR methods, has been widely used in reactor-related research, but the data-driven reduced order model (ROM) shows poor robustness when applied to situations that deviate from the modeling conditions. Therefore, a parametric ROM suitable for estimating the thermal and hydraulic characteristics of OTSG is established in this work by introducing double POD (DPOD). The model is verified based on the full-order model (FOM) developed in the RELAP5 code. Verification results demonstrate that the maximum relative error between the ROM estimations and FOM data is less than 0.5%, while the computational time of the ROM is less than 0.1 s. This parametric ROM thus satisfies the requirements for efficient and accurate estimation of OTSG thermal–hydraulic characteristics, providing a viable alternative to refined simulation models for multi-query simulation tasks and supporting for nuclear digital twins.
通过双正交分解对一次通过式蒸汽发生器进行参数化减阶建模
掌握一次蒸汽发生器(OTSG)的热液压特性对于确保反应堆的稳定运行和安全至关重要。虽然精细的模拟模型可以为 OTSG 热液压研究提供相对准确的预测,但高昂的计算成本往往限制了其在系统在线监测和实时控制中的应用。具体来说,对于优化设计和不确定性分析等多查询仿真任务来说,这些模型的计算负担可能过重。模型阶次缩减(MOR)提供了一种解决方案,可满足核反应堆系统对精度和速度的双重需求。适当正交分解(POD)作为具有代表性的 MOR 方法之一,已被广泛应用于反应堆相关研究中,但数据驱动的降阶模型(ROM)在应用于偏离建模条件的情况时,鲁棒性较差。因此,本研究通过引入双 POD(DPOD),建立了一个适用于估计 OTSG 热和水力特性的参数化 ROM。该模型基于 RELAP5 代码开发的全阶模型(FOM)进行了验证。验证结果表明,ROM 估计值与 FOM 数据之间的最大相对误差小于 0.5%,而 ROM 的计算时间小于 0.1 秒。因此,该参数 ROM 满足了高效、准确估计 OTSG 热液压特性的要求,为多查询仿真任务提供了精炼仿真模型的可行替代方案,并为核数字孪生提供了支持。
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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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