COMBINED ANALYTICAL AND EXPERIMENTAL INVESTIGATIONS FOR LWR CONTAINMENT PHENOMENA

Main focus of the combined nuclear research activities at Aachen University (RWTH) and the Research Center Julich (JULICH) is the experimental and analytical investigation of containment phenomena and processes. We are deeply convinced that reliable simulations for operation, design basis and beyond-design basis accidents of nuclear power plants need the application of so-called lumped-parameter (LP) based codes as well as computational fluid dynamics (CFD) codes in an indispensable manner. The LP code being used at our institutions is the GRS code COCOSYS and the CFD tool is ANSYS CFX mostly used in German nuclear research. Both codes are applied for safety analyses especially of beyond design accidents. Focal point of the work is containment thermal-hydraulics, but source term relevant investigations for aerosol and iodine behavior are performed as well. To increase the capability of COCOSYS and CFX detailed models for specific features, e.g. recombiner behavior including chimney effect, building condenser, and wall condensation are developed and validated against facilities at different scales. The close connection between analytical and experimental activities is notable and identifying feature of the RWTH/JULICH activities.

[1]  Stephan Kelm,et al.  SIMULATION OF MIXING INDUCED BY A HOT PAR EXHAUST PLUME , 2012 .

[2]  Christophe Journeau,et al.  Sustainable integration of EU research in severe accident phenomenology and management. , 2011 .

[3]  F. Ferroni,et al.  Generic approach for designing and implementing a passive autocatalytic recombiner PAR-system in nuclear power plant containments , 2003 .

[4]  C. Spengler,et al.  COCOSYS: Status of development and validation of the German containment code system , 2008 .

[5]  G. Yadigaroglu,et al.  Passive Advanced Light Water Reactor designs and the ALPHA program at the Paul Scherrer Institute , 1998 .

[6]  I. Trubkin.  Experiments and CFD Codes Application to Nuclear Reactor Safety OECD/NEA & International Atomic Energy Agency (IAEA) Workshop , 2008 .

[7]  Man Gyun Na,et al.  UNCERTAINTY ANALYSIS OF DATA-BASED MODELS FOR ESTIMATING COLLAPSE MOMENTS OF WALL-THINNED PIPE BENDS AND ELBOWS , 2012 .

[8]  Hans-Josef Allelein,et al.  Iodine oxides in large-scale THAI tests , 2012 .

[9]  S. Guentay,et al.  The Euratom-Rosatom ERCOSAM-SAMARA projects on containment thermal-hydraulics of current and future LWRs for severe accident management , 2012 .

[10]  P. Peterson.  Diffusion Layer Modeling for Condensation With Multicomponent Noncondensable Gases , 2000 .

[11]  Luis E. Herranz,et al.  Review on condensation on the containment structures , 2009 .

[12]  C. Caroli,et al.  Open issues in the applicability of recombiner experiments and modelling to reactor simulations , 2010 .

[13]  Francesco Saverio D'Auria,et al.  Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants , 2009 .

[14]  J. P. Magnaud,et al.  International standard problem on containment thermal-hydraulics ISP47 Step 1—Results from the MISTRA exercise , 2007 .