@inproceedings{87ab5661b476436f95775256b49bbb92,
title = "Reflooding and boil-off experiments in a VVER-440 like rod bundle and analysis with the CATHARE code",
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.",
author = "Virpi Korteniemi and Timo Haapalehto and Markku Puustinen",
note = "Project code: ene5423; 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7 ; Conference date: 10-09-1995 Through 15-09-1995",
year = "1995",
language = "English",
volume = "1",
series = "NUREG/CP",
publisher = "American Nuclear Society (ANS)",
number = "0142",
pages = "770--780",
editor = "R.C. Block and F. Feiner",
booktitle = "Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7",
address = "United States",
}