核反应堆冷却剂丧失事故下喷淋液滴特性研究  被引量:2

Characteristics of Spray Droplet Under LOCA in Nuclear Power Plant

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作  者:刘家磊[1] 蔡琦[1] 段孟强[2] 张杨伟[1] 

机构地区:[1]海军工程大学核能科学与工程系,湖北武汉430033 [2]海军驻431厂军事代表室,辽宁葫芦岛125005

出  处:《原子能科学技术》2014年第9期1583-1588,共6页Atomic Energy Science and Technology

摘  要:在核反应堆发生冷却剂丧失事故(LOCA)时,大量质能释放到安全壳内,通过喷淋能有效降低安全壳内的温度及压力。考虑喷淋液滴下落过程中体积、质量、温度及阻力系数的变化,应用对流传热及传质关联式,计算得到液滴与周围介质的传热、传质特性。计算结果与TOSQAN试验对比符合较好。对不同液滴尺寸、不同环境压力及蒸汽未达到饱和的情况进行了计算,分析了喷淋的影响,结果可为喷淋系统的设计与应用提供一定的理论依据。When loss-of-coolant accident (LOCA ) occurs in the nuclear power plant ,a lot of mass and energy are released into the containment .The temperature and pressure in the containment can be lowered down effectively by initiating the spray system .Con-sidering the changes of the volume ,mass ,temperature and drag coefficient ,the charac-teristics of heat and mass transfer of the spray droplet to the surroundings were obtained by calculation using the convective heat and mass transfer correlations .T he comparison between the calculation results and the TOSQAN experimental data shows good agree-ment .The cases with different droplet diameters ,different environmental pressures and the case with the steam not reaching saturation state were calculated .By analyzing the effect of the spray ,the results can offer theoretical basis for the spray system design and application .

关 键 词:安全壳 喷淋 液滴 对流传热与传质 

分 类 号:TL364[核科学技术—核技术及应用]

 

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