1995•Unpublished venueOpen access
Reflooding and boil-off experiments in a VVER-440 like rod bundle and analyses with the CATHARE code
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology, V. Korteniemi, American Nuclear Society, La Grange Park, IL (United States), American Inst. of Chemical Engineers, New York, NY (United States), American Society of Mechanical Engineers, New York, NY (United States), Canadian Nuclear Society, Toronto, ON (Canada), Kyoto (Japan) Japan Society of Multiphase Flow, T. Haapalehto, M. Puustinen
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Abstract
Several experiments were performed with the VEERA facility to simulate reflooding and boil-off phenomena in a VVER-440 like rod bundle. The objective of these experiments was to get experience of a full-scale bundle behavior and to create a database for verification of VVER type core models used with modern thermal-hydraulic codes. The VEERA facility used in the experiments is a scaled-down model of the Russian VVER-440 type pressurized water reactors used in Loviisa, Finland. The test section of the facility consists of one full-scale copy of a VVER-440 reactor rod bundle with 126 full-length electrically heated rod simulators. Bottom and top-down reflooding, different modes of emergency core cooling (ECC) injection and the effect of heating power on the heat-up of the rods was studied. In this paper the results of calculations simulating two reflood and one boil-off experiment with the French CATHARE2 thermal-hydraulic code are also presented. Especially the performance of the recently implemented top-down reflood model of the code was studied.