飽和水の液中フラッシングの研究

饱和水淹没冲洗研究

基本信息

批准号：
07650246
负责人：
TAKAMASA Tomoji
金额：
$ 0.06万
依托单位：
Tokyo University of Mercantile Marine
依托单位国家：
日本
项目类别：
Grant-in-Aid for Scientific Research (C)
财政年份：
1995
资助国家：
日本
起止时间：
1995 至 1996
项目状态：
已结题

来源：
https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-07650246/
关键词：
nuclear reactor advanced reactor passive safety loss of coolant accident flashing condensation oscillation linear analysis Pressure aolvanced reactor passive safety reactor water-filling containment LOCA blow-down steam condens

项目摘要

Recently, the research and development on advanced passive safety reactors with a water filled containment have been done in some countries whose aim is at the safety improvement of the nuclear reactor. An experimental study on a saturated high-pressure water discharging into a water pool was performed. The purpose of the experiment is to clarify the phenomena that occur by a blow-down of the water from the pressure vessel into the water-filled containment in the case of a wall-crack accident or a LOCA in a passive safety reactor. The results show that a flashing oscillation (FO) occurs when the water discharges into the pool, under specified experimental conditions. The range of the flashing location oscillates between a point very to and some distance away from the vent hole. The pressures in the vent tube and water pool constantly fluctuate due to the flashing oscillation. The pressure oscillation and alternating flashing location might be caused by the balancing action between the supply of saturated water, flashing at the control volume and steam condensation on the steam-water interface. The frequencies fo FO,or frequencies of pressure oscillation and alternating flashing location, increased as water subcooling increased, and as discharging pressure and vent hole diameter decreased. Nozzle length little affects on the frequency. It means that the location where the flashing occurs and steam generates, at the nozzle side on in the pool, does not affect on the frequency of FO.A linear analysis was conducted using a spherical flashing bubble model in which the motion of bubble is controlled by steam condensation. The effects o these parameters on the period of FO in the experiments can be predicted well by the analysis.

近年来，一些国家正在进行先进非能动安全充水安全壳的研发，旨在提高核反应堆的安全性。对饱和高压水排入水池进行了实验研究。该实验的目的是澄清在非能动安全反应堆发生壁裂事故或失水事故时，水从压力容器排入充水安全壳中所发生的现象。结果表明，在指定的实验条件下，当水排入池中时，会发生闪蒸振荡（FO）。闪光位置的范围在非常接近通风孔的点和远离通风孔一定距离的点之间振荡。由于闪动振荡，通气管和水池内的压力不断波动。压力振荡和闪蒸位置交替可能是由于饱和水供应、控制容积闪蒸和汽水界面上蒸汽冷凝之间的平衡作用引起的。 FO 的频率，即压力振荡和交替闪蒸位置的频率，随着水过冷度的增加以及排放压力和排气孔直径的减小而增加。喷嘴长度对频率影响不大。这意味着闪蒸发生和蒸汽产生的位置（在水池中的喷嘴侧）不会影响 FO 的频率。使用控制气泡运动的球形闪蒸气泡模型进行线性分析通过蒸汽冷凝。通过分析可以很好地预测实验中这些参数对FO周期的影响。