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Experimental and theoretical research on liquid entrainment in AP1000 ADS blow-down phase of SBLOCA

  • Xi'an Jiaotong University
  • State Nuclear Power Technology R and D Center

科研成果: 书/报告/会议事项章节会议稿件同行评审

5 引用 (Scopus)

摘要

The fourth stage Automatic Depressurization System (ADS-4) enables controlled depressurization of reactor coolant system during small break LOCA. However, the coolant may be entrained into the containment through the ADS-4 branch line simultaneously, which reduces the coolant inventory in the primary loop and poses great threats to reactor core uncovering and melting. To make up for the deficiency of liquid entrainment database in advanced passive safety PWR, the Automatic Depressurization and Entrainment TEst Loop (ADETEL) modeled after API000 with a scaling ratio 1:5.6 was constructed, and the test data of ADS-4 entrainment and upper plenum entrainment were collected and analyzed. The experiments were conducted at atmospheric pressure with the maximum steam flow rate of 700kg/h. The entrainment processes were recorded by a high speed camera and interesting details were captured. A clear difference exists between ADETEL ADS-4 entrainment onset data and available correlations, which may caused by the differences in fluids physical properties, horizontal pipe flow conditions, determination methods of entrainment onset and geometries (e.g., diameter ratio between branch and hot leg, d/D). The upper plenum entrainment test data shows that the entrainment deposition effect of the reactor internals is smaller than the entrainment promotion effect due to the decrease of flow area and acceleration of steam in die upper plenum. Using the visualization information gained from experiments, the authors develop a model for predicting the entrainment onset in upward tee branch. The model is compared against the experimental data and shows good agreement.

源语言英语
主期刊名International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
出版商American Nuclear Society
8616-8629
页数14
ISBN(电子版)9781510811843
出版状态已出版 - 2015
活动16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, 美国
期限: 30 8月 20154 9月 2015

出版系列

姓名International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
10

会议

会议16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
国家/地区美国
Chicago
时期30/08/154/09/15

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