2014-2(11)

Design, manufacturing and commissioning of nuclear industry equipment

Article NameNumerical Simulation of Heat Transfer Characteristics of SCWR Fuel Assembly
AuthorsD.S. Grusintsev*, A.S. Shelegov**
Address

Obninsk Institute of nuclear power engineering the Branch of National Research Nuclear University «MEPhI»,
1 Studgorodok, Obninsk, Kaluzhskaya region, Russia 249040
* e-mail: gruzintsev.d@gmail.com ; **
e-mail: a_shelegov@mail.ru

AbstractThe article is devoted to the results of numerical simulation of heat transfer characteristics of a fuel assembly cooled by a water of super critical parameters. It also corresponds about the calculation done for verification of ANSYS CFX code. The authors tell about the verification carried out with the use of empirical correlations for Nusselt criterion. The flow velocity field and temperature distribution are obtained. The results of a simulation in a whole are in agreement with experimental data.
Keywordssupercritical parameters, coolant, fuel assembly, heat transfer, numerical simulation code
LanguageRussian
References

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