Reflooding and boil-off experiments in a VVER-440 like rod bundle and analysis with the CATHARE code

Virpi Korteniemi, Timo Haapalehto, Markku Puustinen

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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.
Original languageEnglish
Title of host publicationProceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7
Subtitle of host publicationSessions 1-5
EditorsR.C. Block, F. Feiner
Place of PublicationLa Grange Park
PublisherAmerican Nuclear Society ANS
Pages770-780
Volume1
Publication statusPublished - 1995
MoE publication typeA4 Article in a conference publication
Event7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7 - Saratoga Springs, United States
Duration: 10 Sep 199515 Sep 1995

Publication series

SeriesNUREG/CP
Number0142
ISSN0270-6482

Conference

Conference7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7
CountryUnited States
CitySaratoga Springs
Period10/09/9515/09/95

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    Korteniemi, V., Haapalehto, T., & Puustinen, M. (1995). Reflooding and boil-off experiments in a VVER-440 like rod bundle and analysis with the CATHARE code. In R. C. Block, & F. Feiner (Eds.), Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7: Sessions 1-5 (Vol. 1, pp. 770-780). American Nuclear Society ANS. NUREG/CP, No. 0142