会议专题

Investigation of Mixing and Thermal Stratification with PIV

The Institute of Nuclear Techniques, Budapest University of Technology and Economics has launched an experimental program to investigate plume mixing and thermal stratification in simple geometries. With the comparison and evaluation of measurement data and Computational Fluid Dynamics (CFD) results the CFD models can be validated. The goal of the work is to develop CFD models to analyse coolant mixing in Pressurized Water Reactor primary pipings and reactor vessel during the use of HPIS or PTS events, especially in WWER-440 reactors 1. For the experiments simple hexahedral plexiglas tanks of different sizes were fabricated. The tanks have five nozzles attached, which can be set up as inlets or outlets depending on the desired measurement configuration. This way several different setups and flow patterns can be investigated using Particle Image Velocimetry (PIV) measurement technique 2. With these methods, two-dimensional velocity fields and temperature distributions of the flow domain can be recorded. The measurement setup consists of flow meters, thermometers, thermocouples to support the PIV system. The engineering environment of the experimental setup enables to use water in the temperature range of 20-80 ℃, and a flow rate in the range of 0.001-0.1 kg/s. With different inlet and outlet configurations and water temperatures inside the tank simulating the stagnating coolant in the primary loop-coolant mixing, thermal stratification and plume behaviour can be investigated. These processes are similar to PTS or HPIS transients. In the paper results of PIV measurements will be presented along with the comparison with the results of CFD simulations. For the calculations ANSYS CFX was used.

Particle Image Velocimetry thermal stratification Computational Fluid Dynamics PWR

Bogdán Yamaji Rita Szijártó Attila Aszódi

Institute of Nuclear Techniques, Budapest University of Technology and Economics 1111 Budapest, Müegyetem rkp. 9., Hungary

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

2045-2058

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)