HYDRA-IBRAE/LM/V1 Thermohydraulic Code Verification Based on BN-600 Experiments


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Abstract

The results of thermohydraulic code HYDRA-IBRAE/LM/V1 verification 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 cool-down regime.

About the authors

I. A. Klimonov

Novosibirsk Branch, Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
Russian Federation, Novosibirsk

E. V. Usov

Novosibirsk Branch, Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
Russian Federation, Novosibirsk

G. A. Dugarov

Novosibirsk Branch, Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
Russian Federation, Novosibirsk

A. A. Butov

Novosibirsk Branch, Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
Russian Federation, Novosibirsk

I. G. Kudashov

Novosibirsk Branch, Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
Russian Federation, Novosibirsk

E. N. Ivanov

Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

N. A. Mosunova

Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

V. F. Strizhov

Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

A. M. Anfimov

Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)

Email: j-atomicenergy@yandex.ru
Russian Federation, Nizhnii Novgorod

V. S. Gorbunov

Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)

Email: j-atomicenergy@yandex.ru
Russian Federation, Nizhnii Novgorod

D. V. Kuznetsov

Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)

Email: j-atomicenergy@yandex.ru
Russian Federation, Nizhnii Novgorod

S. L. Osipov

Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)

Email: j-atomicenergy@yandex.ru
Russian Federation, Nizhnii Novgorod

A. I. Bel’tyukov

Beloyarskaya Nuclear Power Plant, Branch of the Concern Rosenergoatom

Email: j-atomicenergy@yandex.ru
Russian Federation, Zarechnyi

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