Nuclide number density prediction in the lattice physics calculation based on Dynamic mode decomposition

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Shuai Qin , Qian Zhang , Yunfei Zhang , Pengchao Xue , Zhuo Li
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Abstract

Burnup analysis in nuclear reactors requires iterative computation of neutron transport and fuel depletion, which is computationally intensive, particularly for large-scale scenarios. This study introduces an innovative approach leveraging the Dynamic Mode Decomposition (DMD) algorithm to predict the temporal evolution of nuclide densities. By identifying and utilizing the DMD modes and eigenvalues from snapshots of nuclide density, this method aims to alleviate the computational demands of the coupled transport and burnup calculations. Firstly, the methodology selects the key reactivity-contributing nuclides to evaluate the correlation between the complexity of the reduced-order model and the precision of predictions. Subsequently, an optimized reduced-order model is employed for forecasting nuclide densities in a pin-cell. In most cases, DMD predicts more accurately than traditional quadratic extrapolation methods. Moreover, the DMD algorithm demonstrates commendable accuracy in predicting the nuclide density distribution within a PWR fuel assembly, suggesting its promising potential for reactor burnup analysis applications.

基于动态模式分解的晶格物理计算中的核素数量密度预测
核反应堆的燃耗分析需要对中子传输和燃料耗竭进行迭代计算,计算量很大,尤其是在大规模情况下。本研究引入了一种创新方法,利用动态模式分解(DMD)算法来预测核素密度的时间演化。通过识别和利用核素密度快照中的 DMD 模式和特征值,该方法旨在减轻耦合输运和燃耗计算的计算需求。首先,该方法选择关键的反应性贡献核素,以评估降阶模型的复杂性与预测精度之间的相关性。随后,采用优化的降阶模型预测针胞中的核素密度。在大多数情况下,DMD 比传统的二次外推法预测得更准确。此外,DMD 算法在预测压水堆燃料组件内核素密度分布方面表现出了令人称道的准确性,表明其在反应堆燃烧分析应用方面具有广阔的发展前景。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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