A4 Conference proceedings

Reflooding and Boil-off Experiments in VVER-440 Like Rod Bundle and analyses with the CATHARE Code

Open Access publication

Publication Details

Authors: Korteniemi Virpi, Haapalehto Timo, Puustinen Markku

Publication year: 1995

Language: English

Title of parent publication: Proceedings of the 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-7, Sept 10-15, 1995, Saratoga Springs, USA

Start page: 770

End page: 780

Number of pages: 11

JUFO level of this publication: 0

Digital Object Identifier (DOI): http://dx.doi.org/10.2172/107023

Open Access: Open Access publication


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.

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