I.A.Klimonov,E.V.Usov, G.A. Dugarov,A.A.Butov,I.G.Kudashov,E.N.Ivanov,N.A.Mosunova,V.F.Strizhov,A.M.Anfimov,V.S.Gorbunov,D.V.Kuznetsov,S.L.Osipov,A.I.Beltyukov
Выпуск: 5
, Том: 122
, Год издания: 2017
Сериальное издание: Atomic Energy
Страницы: 311-318
Аннотация
The results of thermohydraulic code HYDRA-IBRAE/LM/V1 verifi cation on experimental data obtained using the BN-600 reactor in different years are described. The particulars of the computational scheme of the reactor using HYDRA-IBRAE/LM/V1 for modeling the BN-600 operating regime are presented. In preparing the scheme, special attention was devoted to accurate modeling of the reactor cool-down regimes on natural circulation as being most important from the safety validation standpoint. The computational results obtained with the uncertainty of the initial data taken into account are presented for such a cooldown regime.
