Choking Flow in Supercritical Fluids

超临界流体中的窒息流

• 批准号: 424193-2011
• 负责人: Teyssedou, Alberto
• 金额: $ 7.77万
• 依托单位: École Polytechnique de Montréal
• 依托单位国家: 加拿大
• 项目类别: NSERC/NRCan/AECL Generation IV Energy Technologies Program
• 财政年份: 2013
• 资助国家: 加拿大
• 起止时间: 2013-01-01 至 2014-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=531814
• 关键词: Choking; Flow; Supercritical; Fluids

A particular safety concern in Supercritical Water Reactors (SCWRs) is the estimation of cooling conditions during a postulated Loss-of-Coolant Accident (LOCA) under which choking flow may occur. Such a situation determines both the evolution of the reactor coolant inventory and reactor pressure rate changes. Most of choking flow predictions are based on models developed from subcritical data. To determine whether these models are appropriate or not for supercritical fluids, we present the continuation of a program intended to collect choking flow data using water at supercritical conditions. Thus, a supercritical loop is under construction at École Polytechnique; it consists of a high-pressure, high-temperature branch interconnected to a medium pressure steam-water loop. The high-pressure system is used to control supercritical water flow conditions at the inlet of a test section. The medium pressure loop serves as a pressure controlled reservoir required to achieve continuous steady-state discharge flow experiments with the downstream pressure controlled at will. Different test sections, instrumented with pressure transducers and temperature measurement devices, having different discharge geometries and diameters will be used to study their effects on supercritical choking flows. For different supercritical water inlet conditions, pressure distribution data will be collected by changing and controlling the downstream (discharge) pressure. The experimental information will then be used in model validations. If needed, these data will be used to develop a new model to estimate the choking flow rate at supercritical conditions.

超临界水反应堆（SCWR）的一个特殊安全问题是在假设的失水事故（LOCA）期间可能发生阻塞流的冷却条件的估计。这种情况决定了反应堆冷却剂存量的演变和反应堆压力率的变化。大多数阻塞流预测是基于亚临界数据开发的模型。为了确定这些模型是否适用于超临界流体，我们提出了一个计划，旨在收集窒息流数据，在超临界条件下使用水的延续。因此，一个超临界回路正在巴黎综合理工大学建设中;它由一个高压高温分支与一个中压蒸汽-水回路相连组成。高压系统用于控制试验段入口处的超临界水流条件。中压回路用作压力控制的储液器，以实现连续稳态排放流量实验，并随意控制下游压力。不同的试验段，仪表与压力传感器和温度测量装置，具有不同的排放几何形状和直径将被用来研究它们对超临界阻塞流的影响。对于不同的超临界水入口条件，将通过改变和控制下游（排放）压力来收集压力分布数据。然后将实验信息用于模型验证。如果需要，这些数据将被用来开发一个新的模型，以估计在超临界条件下的阻塞流量。