ANALYSIS OF INFLUENCE OF THE UNCERTAINTIES AVAILABLE WHEN PREPARING THE SMALL-GROUP CONSTANTS ON THE VVER NEUTRONIC CHARACTERISTICS

V.V. BRYUKHIN, M.A. UVAKIN, K.YU. KURAKIN, OKB "GIDROPRESS"

23rd Symposium of AER on VVER Reactor Physics and Reactor Safety (2013, Štrbské Pleso, Slovakia)
Reactor dynamics and safety analysis

Abstract

The thermohydraulic computer code KORSAR is referred to the best estimate codes and
intended to simulate the design and accident conditions of VVER reactor plants. To perform
the coupled neutron-physical and thermal-hydraulic calculations using this computer code the
Code package (CP) SAPFIR_95&RC_VVER is used and by means of the latter the constant
support of program block KARTA, is prepared for the calculation of neutron kinetics of
VVER-type reactor cores in 3-D approximation.

Presentation / full paper