KALININ-3 BENCHMARK CALCULATION WITH COUPLED CODE PARCS-ATHLET

I. Pasichnyk, K. Velkov, GRS Germany, S. Nikonov, VNIIAES, Moscow, Russia

24th Symposium of AER on VVER Reactor Physics and Reactor Safety (2014, Sochi, Russia)
Reactor dynamics and safety analysis

Abstract

KALININ-3 BENCHMARK CALCULATION WITH COUPLED CODE ATHLET-PARCS
Pasichnyk I1., Nikonov S2., Velkov K1.
1Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Garching, Germany {Ihor.Pasichnyk, Kiril.Velkov}@grs.de
2VNIIAES, Moscow, Russia
niks.ki@mail.ru
ABSTRACT
The paper describes and discusses the new developed coupled neutronic/thermal- hydraulic code system based on the version of ATHLET 3.0 thermo-hydraulic code and the three-dimensional multi-group PARCS nodal kinetic code. The coupled code system is applied to analyze an asymmetric transient defined in the OECD/NEA coolant transient Benchmark (K-3) based on measured data at Kalinin-3 Nuclear Power Plant (NPP). The results of the calculation are compared with the set of detailed neutron flux and thermal- hydraulic measurements as well as with other benchmark participants’ calculations.
The main goal of the paper is the generation of a reference solution for further application in the uncertainty and sensitivity studies planned to be performed within the frame of the OECD/NEA UAM Benchmark.

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