Verification of Analytical Test Based Thermohydraulic Systems Codes for One- and Two-Phase Liquid-Metal Flows


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This work is devoted to the development of a system of analytical tests for verification of the thermohydraulic codes used in modeling the flow of one- and two-phase flows of liquid metals. The change of temperature in constant and variable flow of coolant, effect of axial heat conduction of the coolant on the temperature distribution, development of natural circulation in a closed loop, motion of a two-phase mixture under gravity, and fluctuations of the gas volume and distribution of the true process steam content in the presence of boiling/condensation are studied. The developed system of tests was used to verify the HYDRA-IBRAE/LM thermohydraulic code and the thermohydraulic module of the SOKRAT-BN code. The computational errors in the individual thermohydraulic parameters are obtained.

作者简介

E. Usov

Novosibirsk Branch, Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Novosibirsk

A. Butov

Novosibirsk Branch, Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Novosibirsk

I. Klimonov

Novosibirsk Branch, Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Novosibirsk

V. Chukhno

Novosibirsk Branch, Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Novosibirsk

N. Mosunova

Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

R. Chalyi

Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

N. Ryzhov

Nuclear Safety Institute, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

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