The development of the code package PERMAK-3D/SC-1

P.A. Bolobov,D.A. Oleksyuk, NRC "Kurchatov Institute" Moscow, Russia

21st Symposium of AER on VVER Reactor Physics and Reactor Safety (2011, Dresden, Germany)
Spectral and core calculations

Abstract

Code package PERMAK-3D/SC-1 was developed for performing pin-by-pin coupled
neutronic and thermal hydraulic calculation of the core fragment of seven fuel assemblies and
was designed on the basis of 3D multigroup pin-by-pin code PERMAK-3D and 3D
(subchannel) thermal hydraulic code SC-1
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The code package predicts axial and radial pin-by-pin power distribution and coolant
parameters in simulated region (enthalpies, velocities, void fractions, boiling and DNBR
margins). The report describes some new steps in code package development.
Some PERMAK-3D/SC-1 outcomes of VVER calculations are presented in the report.

Presentation / full paper