VVER-1000 Coolant Transient Benchmark - Phase 1 (Vol. 2)

Phase 1 (V1000CT-1), Vol. 2: Summary Results of Exercise 1 on Point Kinetics Plant Simulation

ISBN : 92-64-02295-3
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In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and concepts, as well as current applications.

Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear cores and for the coupling of core phenomena and system dynamics need to be compared against each other and validated against results from experiments. International benchmark studies have been set up for this purpose.

The present volume, a follow-up to the first volume describing the specification of the benchmark, presents the results of the first exercise that identifies the key parameters and important issues concerning the thermal-hydraulic system modelling of the simulated transient. This exercise aims to achieve the correct initialisation and testing of the system code models. The transient chosen for the exercise is caused by the switching on of a main coolant pump while the other three are in operation. It is based on an experiment that was conducted by Bulgarian and Russian engineers during the plant-commissioning phase at the VVER-1000 Kozloduy Unit 6.

NEA classification ID: NEA/NSC/DOC(2006)5