Investigation on heat split in a vertical 3 × 3 dual-cooled annular rod bundle

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-30 DOI:10.1016/j.anucene.2024.111082
Miao Gui , Jingxin Wang , Shan Zhou , Yu Liu , Jianqiang Shan , Yu Liang , Pan Wu
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Abstract

Single-phase heat transfer experiment in a 3 × 3 dual-cooled annular rod bundle was performed to study the heat split behavior and evaluate the applicability of heat transfer correlations to annular fuel. The parametric effects on heat split were investigated. The results showed that the heat split obviously increased with the flow split, and slightly increased with increasing inlet temperature and heating power. The thermal-conduction resistances of gaps played a leading role in heat split mechanism and the convective heat transfer was the secondary factor affecting the heat split. The applicability of heat transfer correlations was assessed by the experimental data. The predictive performance was significantly improved when replacing the hydraulic equivalent diameter by the heated equivalent diameter in the Nusselt number calculation. The DB and El-Genk correlations had the best predictive effect on the heat transfer in the external channel, with the MAE of 0.082 and 0.094 respectively.
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垂直3 × 3双冷环形棒束热分裂研究
在3 × 3双冷环形棒束中进行了单相传热实验,研究了传热行为,并评价了传热关系式对环形燃料的适用性。研究了参数对热分裂的影响。结果表明:随着流量分流的增大,热分流明显增大,随着进口温度和加热功率的增大,热分流略有增大;间隙的热传导阻力在热分裂机制中起主导作用,对流换热是影响热分裂的次要因素。用实验数据对传热关系式的适用性进行了评价。在努塞尔数计算中,用热当量直径代替水力当量直径,预测性能明显提高。DB和El-Genk相关性对外通道换热的预测效果最好,MAE分别为0.082和0.094。
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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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