Exercises 1 and 2 of the VVER-1000 Coolant Transient Benchmark Phase 2 (V1000CT-2) are investigated using coupled three-dimensional (3-D) neutron kinetics/thermal-hydraulics code TRACE/PARCS. Two coarse mesh 3-D thermal-hydraulic models (with six angular sectors and with eighteen angular sectors) were developed for the system code TRACE for Exercise 1 and their applicability is evaluated using ...

As part of the reactor dynamics activities of FZK/IRS, the qualification of a detailed 3D CFD model of a reactor pressure vessel is a key step in safety evaluations for improving predictive capabilities and acceptability of commercial CFD tools in reactor physics. The VVER-1000 Coolant Transient Benchmark, initiated by OECD, represents an excellent opportunity for validation. In this work a CFD...

The presented article discusses developing and validation of a VVER 1000 TRACE V5.0p5 model. Developing such model for computer code is important as it increases the capability analyses in simulating nuclear power plant behaviour different accidents including capabilities 3D thermal hydraulic phenomena reactor core simultaneously with physics calculations. In this way, possible to conduct trans...