BENCHMARKING OF THE 3D CFD CODE GASFLOW II WITH CONTAINMENT THERMAL HYDRAULIC TESTS FROM HDR AND THAI

Abstract

A good understanding of the thermal hydraulic conditions resulting from steam-hydrogen releases in nuclear reactor containments is required for all aspects of accident management and for the design of mitigation measures. The GASFLOW II code has been developed at Forschungszentrum Karlsruhe (FZK) for analysis of such scenarios. It solves the three dimensional compressible transient Navier Stokes equations. This contribution will report on new validations of GASFLOW II with blind and open post-test simulations of experiments that simulate such conditions in the new ThAI containment test facility and in the Heissdampfreaktor (HDR) in Germany.