COMPARISON OF THE RESULTS OF THE 7th DYNAMIC AER BENCHMARK – VVER-440 PRESSURE VESSEL COOLANT MIXING BY RE- CONNECTION OF AN ISOLATED LOOP
24th Symposium of AER on VVER Reactor Physics and Reactor Safety (2014, Sochi, Russia)
Reactor dynamics and safety analysis
Abstract
COMPARISON OF THE RESULTS OF THE 7th DYNAMIC AER BENCHMARK – VVER-440 PRESSURE VESSEL COOLANT MIXING BY RE-CONNECTION OF AN ISOLATED LOOP
Kotsarev A.V., Lizorkin M.P.
NRC «Kurchatov Institute», Moscow, Russia
ABSTRACT
The 7th dynamic benchmark is a continuation of the efforts to validate systematically codes for the estimation of the transient behavior of VVER type nuclear power plants. This benchmark is a continuation of the work in the 6th dynamic benchmark. It is proposed to be simulated the transient – re-connection of an isolated circulating loop with low temperature in a VVER-440 plant. It is supposed to expand the benchmark to other cases when a different number of loops are in operation leading to different symmetric and asymmetric core boundary conditions. The purposes of the proposed benchmark are:
- 1) Best-estimate simulations of an transient with a coolant flow mixing in the Reactor Pressure Vessel (RPV) of VVER-440 plant by re-connection of one coolant loop to the several ones on operation,
- 2) Performing of code-to-code comparisons.
Solutions were received from National Research Centre “Kurchatov Institute” (ATHLET/BIPR-VVER), UJV Rez (RELAP-3D) and HZDR (DYN3D/ATHLET). This paper gives an overview on the behaviour of the main thermohydraulic and neutron kinetic parameters in the provided solutions.