A subchannel analysis code for advanced liquid metal fast reactor cores and study on heat transfer characteristics of core geometry parameters

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2024-10-07 DOI:10.1016/j.pnucene.2024.105477

Bin Han , Yuanyuan Yin , Xiaoliang Zhu , Bao-Wen Yang , Shenghui Liu , Lingping Song , Aiguo Liu , Tianyang Xing

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引用次数: 0

Abstract

The liquid metal fast reactor represents an important reactor type for the future development of nuclear energy. Accurately modeling and predicting the subchannel flow and heat transfer phenomenon in the rod bundles plays a key role in ensuring core safety. Consequently, a subchannel code suitable for the liquid metal fast reactor is analyzed based on the subchannel analysis code of the Pressurized Water Reactor (PWR). The modified code incorporates various types of liquid metals, such as lead, lead-bismuth eutectic (LBE), and sodium, along with their constitutive models, enhancing the applicability of the liquid metal reactor systems. This code has been verified and validated at several levels, including comparing the code simulation results with other similar subchannel codes results, high-dimensional Computational Fluid Dynamics (CFD) simulations, and experiment data. The sensitivity analysis of core geometric parameters and turbulent mixing coefficients is performed based on the modified version code. The influence of the core geometry, including the rod Pitch to Diameter ratio (P/D), Rod to Wall gap (RTW) and the wire wrap pitch (H) on the sensitivity of outlet temperature has been investigated. The results show that the new subchannel analysis code suitable for liquid metal cooled reactor shows reasonable agreement with the verified and validated results. The geometric parameters, such as P/D, RTW and H have noticeable effects on the outlet temperature difference of the subchannels. Additionally, the outlet temperature distribution in the subchannel is significantly affected by different turbulent mixing coefficients and the distribution of the turbulent mixing coefficient also influenced by the reactor core sizes. Overall, this study could support the rod bundles design and safety analysis in the liquid metal reactors.

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先进液态金属快堆堆芯子通道分析代码及堆芯几何参数传热特性研究

液态金属快堆是未来核能发展的重要堆型。准确模拟和预测棒束中的副通道流动和传热现象对确保堆芯安全起着关键作用。因此，在压水堆子通道分析代码的基础上，分析了适合液态金属快堆的子通道代码。修改后的代码纳入了各种类型的液态金属，如铅、铅铋共晶（LBE）和钠，以及它们的构成模型，增强了液态金属反应堆系统的适用性。该代码在多个层面上进行了验证和确认，包括将代码模拟结果与其他类似子通道代码结果、高维计算流体动力学（CFD）模拟和实验数据进行比较。在修改版代码的基础上，对核心几何参数和湍流混合系数进行了敏感性分析。研究了核心几何参数，包括杆距直径比 (P/D)、杆壁间隙 (RTW) 和绕线间距 (H) 对出口温度灵敏度的影响。结果表明，适用于液态金属冷却反应堆的新子通道分析代码与经过验证和确认的结果显示出合理的一致性。P/D、RTW 和 H 等几何参数对子通道出口温差有明显影响。此外，子通道的出口温度分布受不同湍流混合系数的显著影响，而湍流混合系数的分布也受反应器堆芯尺寸的影响。总之，这项研究可为液态金属反应堆的棒束设计和安全分析提供支持。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.