VVER-1000 Coolant Transient Benchmark

Phase 2 (V1000CT-2) Summary Results of Exercise 1 on Vessel Mixing Simulation

ISBN : 978-92-64-99152-1
- Adobe Acrobat PDF Document on 12/20/19 at 2:51 PM

Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and compared with each other to help understand how the different modelling methods adopted affect the accuracy of the simulation. This benchmark was set up for that purpose.

This report is one of a series covering benchmarks designed to test modelling methods for a range of transient scenarios in a VVER-1000 reactor. In this case, the transient is initiated by isolation of one steam generator causing asymmetric loop heat-up. The benchmark is based on experiments conducted at the Kozloduy nuclear power plant.