https://hal-cea.archives-ouvertes.fr/cea-02355776/document

International standard problem on containment thermal–hydraulics ISP47: Step 1—Results from the MISTRA exercise

An intercomparison exercise on the capabilities of CFD models to predict distribution and mixing of H2 in a closed vessel

Analysis of steam and hydrogen distributions with PAR mitigation in NPP containments

A review on hydrogen generation, explosion, and mitigation during severe accidents in light water nuclear reactors

https://catatanstudi.files.wordpress.com/2009/11/2008-validation-of-the-cfx4-cfd-code-for-containment-thermal-hydraulics_houkema.pdf

Validation of the CFX4 CFD code for containment thermal-hydraulics

Three-dimensional all-speed CFD code for safety analysis of nuclear reactor containment: Status of GASFLOW parallelization, model development, validation and application

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.

/pdf/benchmarking-of-the-3d-cfd-code-gasflow-ii-with-containment-3ax37a8vhl.pdf

Benchmarking of the 3d cfd code gasflow ii with containment thermal hydraulic tests from hdr and thai

The CFD code GASFLOW solves the time-dependent compressible Navier-Stokes Equations with multiple gas species. GASFLOW was developed for nonnuclear and nuclear applications. The major nuclear applications of GASFLOW are 3D analyses of steam/hydrogen distributions in complex PWR containment buildings to simulate scenarios of beyond design basis accidents. Validation of GASFLOW has been a continuously ongoing process together with the development of this code. This contribution reports the results from the open posttest GASFLOW calculations that have been performed for new experiments from the OECD SETH Benchmark. Discussed are the steam distribution tests 9 and 9bis, 21 and 21bis involving comparable sequences with and without steam condensation and the last SETH test 25 with steam/helium release and condensation. The latter one involves lighter gas mixture sources like they can result in real accidents. The helium is taken as simulant for hydrogen.

/pdf/gasflow-validation-with-panda-tests-from-the-oecd-seth-1ggoo7vrgh.pdf

P. Royl

Papers

Analysis of steam and hydrogen distributions with PAR mitigation in NPP containments

Three-dimensional all-speed CFD code for safety analysis of nuclear reactor containment: Status of GASFLOW parallelization, model development, validation and application

Benchmarking of the 3d cfd code gasflow ii with containment thermal hydraulic tests from hdr and thai

GASFLOW Validation with Panda Tests from the OECD SETH Benchmark Covering Steam/Air and Steam/Helium/Air Mixtures

CFD analysis of hydrogen volumetric concentrations in a Hard Venting Containment System of a Mark II BWR