Experimental and computational studies of two-phase flows in nuclear reactor systems

核反应堆系统中两相流的实验和计算研究

• 批准号: 449458-2013
• 负责人: Tavoularis, Stavros
• 金额: $ 2.19万
• 依托单位: University of Ottawa
• 依托单位国家: 加拿大
• 项目类别: Collaborative Research and Development Grants
• 财政年份: 2016
• 资助国家: 加拿大
• 起止时间: 2016-01-01 至 2017-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=597104
• 关键词: Experimental; computational; studies; two; phase

Mixtures of gas and liquid flows are commonly encountered in heat exchangers, in components of nuclear reactors and other equipment in which boiling or condensation occurs. Such flows are very complex, but recent advances in measurement techniques and computational methods have permitted an in-depth examination of their characteristics. The objective of this project is to apply, and further develop, available experimental and computational fluid dynamics (CFD) methods to the study of two-phase flow characteristics in header-feeder systems of the type used in CANDU nuclear power plants. The main experimental tasks are: i) to modify an existing air-water flow loop by the addition of a versatile header/feeder model, in which different combinations of active inlet turrets and active feeders can be selected; ii) to assemble a database of measurements of gas and liquid flow rates in the feeder tubes of this model, while also documenting the turret inlet conditions and the flow patterns inside the header; and iii) to assess the effect of flow obstructions inside feeder tubes on the gas and liquid flow rates. The main task of the computational analysis is to perform CFD simulations of air-water flows at the same inlet flow conditions and in the same geometries as those of the experiments and to compare the simulation results to the measurements to verify the applicability of CFD as a tool for two-phase flow simulation at conditions and geometries of interest to nuclear safety analysis. The proposed experimental and numerical investigations will be conducted using state-of-the-art tools and will advance the technical capabilities of nuclear reactor designers and safety analysts. They are in direct support of the AECL air-water header facility tests. They will also assist the Canadian nuclear power industry in validating and improving existing multi-phase analytical tools and in maintaining a competitive position in this field of the world economy. This grant will enable uOttawa to educate several students and other personnel in nuclear reactor thermalhydraulics, thus providing the nuclear industry with a pool of prospective highly skilled research engineers to replace the currently retiring generation of such personnel.

在热交换器，核反应堆和其他沸腾或冷凝的设备的组件中，通常会遇到气体和液体流量的混合物。这样的流程非常复杂，但是测量技术和计算方法的最新进展允许对其特征进行深入研究。该项目的目的是应用并进一步开发可用的实验和计算流体动力学（CFD）方法，以研究Candu核电站使用类型的标头馈线系统中的两相流量特征。主要的实验任务是：i）通过添加多功能标头/馈线模型来修改现有的空气水流动环，其中可以选择主动入口炮塔和活动馈线的不同组合； ii）要组装该模型馈线管中气体和液体流速的测量数据库，同时还记录了炮塔入口条件和标头内的流动模式； iii）评估馈线管内流动阻塞对气体和液体流速的影响。计算分析的主要任务是在相同的入口流量条件下和与实验的几何形状下对空气水流进行CFD模拟，并将模拟结果与测量结果进行比较，以验证CFD作为CFD的适用性在核安全分析的条件和感兴趣的几何形状下进行两相流仿真的工具。拟议的实验和数值研究将使用最先进的工具进行，并将提高核反应堆设计师和安全分析师的技术能力。他们直接支持AECL空气水域设施测试。他们还将帮助加拿大核电行业验证和改善现有的多相分析工具，并在世界经济的这一领域保持竞争地位。这笔赠款将使乌塔瓦能够教育几名学生和其他人员在核反应堆热液中，从而为核工业提供了一大批潜在的高技能研究工程师，以取代目前退休的这一人员。