A comparative analysis of detailed and reduced CFD approaches to model wire-wrapped fuel bundles for LMFBRs applications

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2024-10-03 DOI:10.1016/j.anucene.2024.110937

O. Halim , F. Galleni , N. Forgione , I. Di Piazza , A. Pucciarelli

引用次数: 0

Abstract

The paper investigates the capabilities of different CFD modelling approaches in reproducing operating conditions relevant for Liquid Metal Fast Breeder Reactors technologies. The selected benchmark is the NACIE-UP facility wire-wrapped fuel bundle using Lead-Bismuth Eutectic (LBE) as coolant: the predictions are compared to the experimental data collected for several operating conditions considered in the frame of two distinct experimental campaigns. Four different modelling approaches have been adopted in this work to model the NACIE-UP Fuel Pin Simulator: Bare, Detailed, Solid-Wire and the Porous-Wire Rod Bundle model. A model-to-model comparison is performed to understand the benefits, limitations, and accuracy of using different modelling approaches for representing wrapped wires fuel bundles. Furthermore, integrating NACIE-UP benchmark experimental data into the comparative analysis reinforce the validation process of the adopted modelling approaches.

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详细和简化 CFD 方法的比较分析，以模拟低密度纤维束燃料元件应用中的线包燃料束

本文研究了不同 CFD 建模方法在再现液态金属快中子增殖反应堆技术相关运行条件方面的能力。选定的基准是使用铅铋共晶（LBE）作为冷却剂的 NACIE-UP 设施线包燃料束：将预测结果与在两个不同实验活动框架内考虑的几种运行条件下收集的实验数据进行了比较。这项工作采用了四种不同的建模方法对 NACIE-UP 燃料针模拟器进行建模：裸模型、详细模型、实心线模型和多孔线棒束模型。通过模型与模型之间的比较，可以了解使用不同建模方法表示包线燃料束的优点、局限性和准确性。此外，将 NACIE-UP 基准实验数据纳入比较分析，加强了所采用建模方法的验证过程。

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

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.