THE THERMOMECHANICAL MODEL USED IN THE MODULE OF CODE ATHLET\BIPR-VVER FOR A QUANTITY ESTIMATION FAILURED FUEL RODS IN ACCIDENTS RIA
22nd Symposium of AER on VVER Reactor Physics and Reactor Safety (2012, Průhonice, Czech Republic)
NEUTRON KINETICS AND REACTOR DYNAMICS METHODS
In the paper, the basic results on working out of modules of thermomechanical calculation
for the analysis of the fuel rod behaviour in RIA type accidents according to requirements of
integrated code ATHLET/BIPR-VVER are stated.
Integrated code ATHLET/BIPR-VVER provides calculation of necessary neutronphysical and heat-hydraulic parameters representative fuel rods for the program of “mechanical”
fuel rod calculation (parameters of the stressed-deformed state and the mechanic of
The module of an estimation of parameters of a preemergency condition representative
fuel rod contains a necessary set of correlations for their conservative estimation. It is necessary
to underline, that this module is under construction by a principle of the minimum sufficiency
for the emergency analysis, and for reception of more realistic estimation, the given module can
be replaced with the interface of the resource fuel rod code.
The description of total modules is presented.