Influence of Non-Condensable Gas-Dust Mixture On Direct Contact Condensation of Steam At Atmospheric Pressure

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-11-18 DOI:10.1115/1.4064066
Luca Berti, A. Pesetti, M. Raucci, Guglielmo Giambartolomei, D. Aquaro
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Abstract

At the Department of Civil and Industrial Engineering (DICI) of the University of Pisa, an experimental research program, funded by ITER Organization, concerning steam direct condensation in a flux containing also non-condensable gas and dust, was carried out. This mixture of fluids and dust is injected into the ITER Pressure Suppression Tanks during a Loss of Coolant Accident in the Vacuum Vessel. The aim of the research program is to determine the steam condensation efficiency in such conditions. Experimental tests were performed injecting this mixture in a tank partially filled with water. Alumina was used to simulate the actual dust present in the ITER Vacuum Vessel. Mass flow rates, temperature and pressure of the different fluids involved were recorded during the tests. The steam condensation into the subcooled water pool at a temperature ranging between 20 and 100°C was investigated to determine the condensation regimes occurring during the mixture injection. The values of the fraction of the energy absorbed by water, dust and metallic structures, of the heat losses and of the average heat transfer coefficient were determined considering pure steam, steam-dust and steam-air-dust injection. The average heat transfer coefficient, determined calculating the steam jet surfaces by means of image elaboration, was compared with empirical correlations.
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不凝气-粉尘混合物对常压下蒸汽直接接触凝结的影响
比萨大学(University of Pisa)土木与工业工程系(DICI)在热核实验堆组织的资助下开展了一项实验研究计划,研究内容是蒸汽在同时含有非凝结气体和粉尘的通量中的直接凝结。在真空容器发生冷却剂损失事故时,这种流体和灰尘混合物会被注入热核实验堆压力抑制罐。研究计划的目的是确定这种情况下的蒸汽冷凝效率。实验测试将这种混合物注入部分注满水的水箱中。氧化铝被用来模拟热核实验堆真空容器中实际存在的灰尘。试验期间记录了不同流体的质量流量、温度和压力。 研究了蒸汽在 20 至 100 摄氏度之间的过冷水池中的冷凝情况,以确定混合物注入过程中出现的冷凝状态。考虑到纯蒸汽、蒸汽-粉尘和蒸汽-空气-粉尘喷射,确定了水、粉尘和金属结构吸收的能量比例值、热损失和平均传热系数。通过图像处理计算蒸汽喷射表面得出的平均传热系数与经验相关系数进行了比较。
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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