当前位置: X-MOL 学术Measurement › 论文详情
Our official English website, www.x-mol.net, welcomes your feedback! (Note: you will need to create a separate account there.)
Measurements for verification and validation of thermal-hydraulic computer code used for thermal-hydraulic analysis of VVER440 typical fuel assembly
Measurement ( IF 5.2 ) Pub Date : 2020-12-01 , DOI: 10.1016/j.measurement.2020.108787
György Ézsöl , Ezddin Hutli , Gottlasz Valér , Zsiros Gábor

The paper contains experimental data and analysis of the velocity distribution and pressure drop of turbulent flow through a fuel bundle of 19 rods as a partial model of the VVER-440 reactor core. Also, results from the code calculations at the outlet of the test assembly at different flow rates and comparison with experimental data are presented. A pitot tube was used to measure the velocity and pressure drop. Detailed measurements of the velocity distribution in a fuel bundle are done in a fully developed turbulent flow region. Moreover, detailed measurements of the pressure drop of wire and spacer grids typical for PWRs are discussed together with the total pressure drops performance. The experimental result was compared with the predictions by our code and good agreement was found. The calibration protocol and uncertainties of the measurements are presented.



中文翻译:

用于验证和确认VVER440典型燃料组件的热工分析的热工计算机代码的测量

本文包含实验数据,并分析了通过19根燃料棒束作为VVER-440反应堆堆芯的部分模型的湍流的速度分布和压降。此外,还给出了在不同流速下测试组件出口处的代码计算结果以及与实验数据的比较结果。皮托管用于测量速度和压降。燃料束中速度分布的详细测量在完全展开的湍流区域中进行。此外,还讨论了压水堆典型的线网和隔栅的压降的详细测量以及总压降性能。通过我们的代码将实验结果与预测结果进行了比较,并发现了很好的一致性。

更新日期:2020-12-16
down
wechat
bug