Lead coolant modeling in system thermal-hydraulic code HYDRA-IBRAE/LM and some validation results

N.A. Mosunova,V.M. Alipchenkov,N.A. Pribaturin,V.F. Strizhov,E.V. Usov,P.D. Lobanov,D.A. Afremov, A.A. Semchenkov, I.A. Larin

Nuclear Engineering and Design（2020）

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摘要

•The thermal-hydraulic code HYDRA-IBRAE/LM allows modeling installations with lead coolant.•The HYDRA-IBRAE/LM code is validated on the experiments conducted with lead coolant.•Flow regime map and closure relations for lead coolant modelling have been formulated.•A representative database of experimental data obtained for lead has been formed in Russia.

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关键词

HYDRA-IBRAE/LM,System code,Lead coolant,Closure relations,Validation

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