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Scaling methodology for a reduced-height reduced-pressure integral test facility to investigate direct vessel injection line break SBLOCA

机译:用于减小高度的减压整体测试设备的缩放方法,以研究直接容器注入管线中断SBLOCA

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A scaling methodology for a small-scale integral test facility was investigated in order to analyze thermal-hydraulic phenomena during a DVI (direct vessel injection) line SBLOCA (small break loss-of-coolant accident) in an APR1400 (advanced power reactor 1400 MWe) pressurized water reactor. The test facility SNUF (Seoul National University Facility) was utilized as a reduced-height and reduced-pressure integral test loop. To determine suitable test conditions for simulating the prototype in the SNUF experiment, the energy scaling methodology was propose to scale the coolant mass inventory and the thermal power for a reduced-pressure condition. The energy scaling methodology was validated with a system code (MARS) analysis for an ideally scaled-down SNUF model and that predicted a reasonable transient of pressure and coolant inventory when compared to the prototype model. For the actually constructed SNUF, the effect of scaling distortions in the test facility's thermal power and the loop geometry was analytically investigated. To overcome the limitation of the thermal power supply in the facility, the convective heat transfer between primary and secondary systems at the steam generator U-tubes was excluded and a modified power curve was applied for simulating the core decay heat. From the code analysis results for the actual SNUF model, the application of the modified power curve did not affect the major events occurring during the transient condition. The results revealed that the scaling distortion in the actual SNUF geometry also did not strongly disturb significant thermal-hydraulic phenomena such as the downcomer seal clearing. Thus, with an adoption of the energy scaling methodology, the thermal-hydraulic phenomena observed in the SNUF experiment can be properly utilized in a safety analysis for a DVI line break SBLOCA in the APR1400.
机译:为了分析APR1400(先进功率反应堆1400 MWe)中的DVI(直接容器注入)管线SBLOCA(小冷却剂损失小事故)期间的热工现象,研究了一种小型整体测试设施的缩放方法。 )压水堆。测试设备SNUF(首尔国立大学设备)被用作减小高度和减小压力的整体测试回路。为了确定在SNUF实验中模拟原型的合适测试条件,提出了一种能量缩放方法,用于在减压条件下缩放冷却剂的质量存量和火力。能量缩放方法论已通过系统代码(MARS)分析进行了验证,可用于理想比例缩小的SNUF模型,并且与原型模型相比,该模型可预测压力和冷却剂存量的合理过渡。对于实际构建的SNUF,通过分析研究了缩放比例失真对测试设备的热功率和环路几何形状的影响。为了克服设施中热能供应的限制,排除了蒸汽发生器U型管的一次和二次系统之间的对流传热,并应用了修正的功率曲线来模拟堆芯衰减热。从实际SNUF模型的代码分析结果来看,修改后的功率曲线的应用不会影响瞬态条件下发生的主要事件。结果表明,实际SNUF几何形状中的水垢变形也没有强烈干扰显着的热工现象,例如降液管密封件的清除。因此,通过采用能量缩放方法,可以将SNUF实验中观察到的热工现象适当地用于APR1400中DVI断线SBLOCA的安全性分析中。

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