Open AccessMIXED CORE SUBCHANNEL MODEL FOR SUBCAL AND COUPLING WITH ANDREA
Author(s) -
Vojtěch Caha,
J. Čı́žek
Publication year - 2018
Publication title -
acta polytechnica ctu proceedings
Language(s) - English
Resource type - Journals
ISSN - 2336-5382
DOI - 10.14311/app.2018.19.0001
Subject(s) - core (optical fiber) , homogeneous , flow (mathematics) , coupling (piping) , nuclear engineering , mechanics , thermal hydraulics , coolant , nuclear reactor core , materials science , physics , computer science , simulation , thermodynamics , mechanical engineering , engineering , heat transfer , composite material
This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisting of fuel assemblies with non-identical spacing grids. The calculation was carried out using the modified subchannel code SUBCAL-AZ which allows to calculate 3D thermal-hydraulic characteristics of the coolant flow in the full core subchannel model coupled with the neutron-physical code ANDREA. This full core subchannel model was created in three variants depending on the ANDREA calculations. The first variant (homogeneous core) consisted of 163 hydraulically identical fuel assemblies TVSA-T mod.2, whereas the other variants (mixed cores) consisted of fuel assemblies TVSA-T mod.0, mod.1 and mod.2. These fuel assemblies mainly differ in types, number and axial coordinate of spacing grids and also in diameter of guide tubes. The influence of mixed core to flow distribution was obtained by comparing these variants.