Numerical study on benchmark analysis of NACIE-UP facility with uniform and non-uniform power distribution

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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Abstract

The NACIE-UP (NAtural Circulation Experiment-Upgrade) facility is located at the ENEA Brasimone Research Centre (Italy) and is designed to investigate the thermal–hydraulic properties of Lead-Bismuth Eutectic (LBE) within a wire-spaced assembly under uniform and non-uniform power distribution conditions. This benchmark exercise proposed by ENEA is based on previous experiment results, intending for development and validation of CFD/TH system code, stand-alone CFD simulation, etc. In this study, the thermal–hydraulic characteristics of Fuel Pin Simulator (FPS) are analyzed, which contains inlet bend and outlet section. ANSYS Fluent solver is applied with the COUPLE algorithm of RANS SSTk-ω model. Cheng&Tak correlation and computational conditions are implanted into Fluent in the form of UDFs. Moreover, calculations were performed for ADP10, ADP06 and ADP07. The results show that the RMSEs of ADP10SS1 and ADP10SS2 are 2.52 K and 3.69 K, 7.05 K and 8.48 K for ADP06SS1 and ADP06SS2, respectively, which indicate that the adopted models have good prediction ability for the temperature of the experimental conditions. Meanwhile, the heat transfer characteristics of different sub-channels and sections are investigated and compared with the correlations of Ushakov, Mikityuk, Kazimi and Carelli. The experimental and simulation values of the uniformly heated ADP10 are in good agreement with the correlations, while there is a large deviation for the non-uniformly heated ADP06. Therefore, it is necessary to develop new correlations for the heat transfer characteristics of LBE in wire-wrapped bundle. Above all, this study provides quantitative and qualitative analysis for verification and validation of CFD/TH system code and stand-alone CFD simulation.

均匀和非均匀功率分布的 NACIE-UP 设施基准分析数值研究
NACIE-UP(NAtural Circulation Experiment-Upgrade)设施位于 ENEA Brasimone 研究中心(意大利),旨在研究均匀和非均匀功率分布条件下铅铋共晶(LBE)在导线间隔组件内的热液压特性。ENEA 提出的这一基准练习基于之前的实验结果,旨在开发和验证 CFD/TH 系统代码、独立 CFD 仿真等。本研究分析了燃料针模拟器(FPS)的热液压特性,其中包括入口弯管和出口部分。ANSYS Fluent 仿真器采用了 RANS SSTk-ω 模型的 COUPLE 算法。Cheng&Tak 相关性和计算条件以 UDF 的形式植入 Fluent。此外,还对 ADP10、ADP06 和 ADP07 进行了计算。结果表明,ADP10SS1 和 ADP10SS2 的均方根误差分别为 2.52 K 和 3.69 K,ADP06SS1 和 ADP06SS2 的均方根误差分别为 7.05 K 和 8.48 K,表明所采用的模型对实验条件下的温度具有良好的预测能力。同时,研究了不同子通道和截面的传热特性,并与 Ushakov、Mikityuk、Kazimi 和 Carelli 的相关系数进行了比较。均匀加热的 ADP10 的实验值和模拟值与相关系数十分吻合,而非均匀加热的 ADP06 则存在较大偏差。因此,有必要针对线包束中 LBE 的传热特性建立新的相关关系。总之,本研究为 CFD/TH 系统代码和独立 CFD 模拟的验证和确认提供了定量和定性分析。
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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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