Ontology type: schema:ScholarlyArticle
2021-11-03
AUTHORSA. A. Butov, I. A. Kliminov, I. G. Kudashov, V. I. Chukhno, T. V. Sycheva, E. V. Usov, N. A. Mosunova, V. F. Strizhov
ABSTRACT—The second version of the EUCLID/V integrated code, denoted by EUCLID/V2, has been developed for analyzing the processes occurring in the course of severe accidents in sodium-cooled reactor plants with uranium dioxide fuel. Within the verification of this version that uses a 3D thermal-hydraulic module, modeling was carried out, and the prediction results were compared with the experimental data obtained on experimental setups in Germany and France on simulating accidents involving partial and complete blockage of the flow section (the first type) and also with loss of coolant flowrate (the second type). The experiments on simulating an accident involving partial blockage of the flow pass section in a 169-pin assembly (KNS 169) and on simulating an accident involving complete blockage of the flow pass section in a 37-pin assembly (SCARABEE-N BE+3) correspond to accidents of the first type, and experiments on simulating an ULOF type accident in a 37-pin assembly (KNS 37) correspond to accidents of the second type. Based on calculations carried out taking into account the available experimental data, the correctness of modeling performed using the EUCLID/V2 integrated code 3D thermal-hydraulic module is estimated, and the error of the coolant and fuel pin cladding temperatures predicted using the presented code is determined. More... »
PAGES841-847
http://scigraph.springernature.com/pub.10.1134/s0040601521090019
DOIhttp://dx.doi.org/10.1134/s0040601521090019
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