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ISSN Online: 2379-1748

ISBN Flash Drive: 978-1-56700-469-4

ISBN Online: 978-1-56700-470-0

Second Thermal and Fluids Engineering Conference
April, 2-5, 2017, Las Vegas, NV, USA

EXPERIMENTAL STUDY ON THE BLOWDOWN LOAD DURING THE STEAM GENERATOR STEAM LINE BREAK ACCIDENT IN THE EVOLUTIONARY PRESSURIZED WATER REACTOR

Get access (open in a dialog) pages 2491-2494
DOI: 10.1615/TFEC2017.ist.017820

要約

A sudden break of a steam generator steam line can induce an anticipated hydrodynamic load on the internal structures of a steam generator. From a structural integrity point of view, a precise prediction on the hydrodynamic load during the steam generator feedwater line break is important for a safety analysis of nuclear power plant. Integral effect tests using the ATLAS facility were performed to obtain the thermal-hydraulic parameters such as dynamic and static pressures, local temperatures, and flow rates during a steam line break of a steam generator. Break of a steam line was simulated using a double rupture disc assembly for satisfying the requirement for the break opening time around a few milliseconds. In the present work, estimated break opening time was less than 1.4 ms and broken areas were 100 % of the steam line, respectively. The maximum dynamic pressure was obtained at the steam outlet nozzle end where it was closest to the break spool of the steam line. After the break opening of the steam line, propagation of the pressure wave along the flow line inside the steam generator was not clearly observed in the present tests. Especially, the variations of dynamic pressures measured inside the steam dome and the outlet region of steam separator were trivial. This result indicates that the dynamic pressure wave was dampened during the propagation process inside the steam generator in case of the steam line break accident. From a qualitative point of view, it could be found that the steam line break accident does not produce significant hydrodynamic load propagated inside the steam generator.