Experimental and theoretical research on upper plenum entrainment with air-water and steam-water

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2024-11-06 DOI:10.1016/j.pnucene.2024.105525
Kepiao Li , Zhiyuan Wu , Kui Zhang , Wenxi Tian , Suizheng Qiu
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Abstract

Upper plenum entrainment phenomenon occurs in the automatic depressurization process during the Small Break Loss of Coolant Accident (SBLOCA) in reactor pressure vessel, which may result in reactor disaster. The upper plenum entrainment experiments with and without reactor internals were carried out with air-water and steam-water as working mediums on the Automatic Depressurization and Entrainment Test Loop for Upper plenum entrainment (ADETEL-U) which scaled after AP1000 nuclear reactor. The experimental phenomena were observed by visualization method and the reliable data were collected and analyzed. The results indicate that the entrainment rate will increase with the increase of gas flow rate under the same hg, and the entrainment rate will decrease significantly with the decrease of the mixed liquid level when the range of hg is low. The results confirm that a large number of liquid droplets will be deposited on the surface of the reactor internals, which greatly reduces the entrainment rate. Under the same conditions, the entrainment rate with the reactor internals is about 10% of that without the reactor internals. There is a huge discrepancy between the existing pool entrainment rate models and the experimental data, with the maximum deviation of 200 times. Based on the experimental results, new upper plenum entrainment models for near surface region and high gas flux region of momentum controlled region are proposed. The error decreases by orders of magnitude compared to existing models, which suggested that the new model can accurately predict upper plenum entrainment phenomenon in the pressure vessel.
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空气-水和蒸汽-水的上部柱流夹带实验和理论研究
在反应堆压力容器发生小断裂失冷却剂事故(SBLOCA)时,自动减压过程中会出现上部柱体夹带现象,可能导致反应堆灾难。以 AP1000 核反应堆为原型的上柱面自动减压和夹杂试验环路(ADETEL-U)以空气-水和蒸汽-水为工作介质,进行了有反应堆内部构件和无反应堆内部构件的上柱面夹杂实验。采用可视化方法观察了实验现象,并收集和分析了可靠数据。结果表明,在相同的 hg∗ 条件下,夹带率会随着气体流量的增加而增加;当 hg∗ 范围较低时,夹带率会随着混合液液面的降低而显著降低。结果证实,大量液滴会沉积在反应器内件表面,从而大大降低了夹带率。在相同条件下,有反应器内件的夹带率约为无反应器内件的 10%。现有的水池夹带率模型与实验数据存在巨大差异,最大偏差达 200 倍。根据实验结果,提出了动量控制区近表面区域和高气体通量区域的新的上柱体夹带模型。与现有模型相比,误差减小了几个数量级,这表明新模型可以准确预测压力容器中的上柱体夹带现象。
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来源期刊
Progress in Nuclear Energy
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.
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