THAI experimental programme for containment safety assessment under severe accident conditions
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S. Gupta
Abstract
The THAI (THAI = Thermal hydraulics, Hydrogen, Aerosols, Iodine) experimental programme aims to address open questions concerning the behavior of hydrogen, iodine and aerosols in the containment of water cooled reactors. Since its construction in 2000, THAI programme is being performed in the frame of various national projects (sponsored by German Federal Ministry for Economic Affairs and Energy, BMWi) and two international joint projects (under auspices of OECD/NEA). THAI experimental data have been widely used for the validation and further development of Lumped Parameter (LP) and Computational Fluid Dynamics (CFD) codes with 3D capabilities. Selected examples of code benchmark exercises performed based on the THAI data include; hydrogen distribution experiment (ISP-47 and OECD/NEA THAI code benchmark), hydrogen combustion behaviour (ISP-49), hydrogen mitigation by PARs (OECD/NEA THAI-2 code benchmark), iodine/surface interactions, iodine mass transfer, and iodine transport and multi-compartment behaviour (EU-SARNET and EU-SARNET2), thermal-hydraulic tests (German CFD-network). In the present paper, a brief overview on the THAI experiments and their role in the containment safety assessment is discussed.
Kurzfassung
Die Versuchsprogramme in der THAI-Versuchsanlage dienen der Klärung offener Fragen zur Thermohydraulik sowie zum Verhalten von Wasserstoff, Iod, und Aerosolen im Sicherheitsbehälter von wassergekühlten Reaktoren (THAI = Thermal-Hydraulics, Hydrogen, Aerosols, Iodine). Seit seiner Inbetriebnahme im Jahr 2000 wurden mehrere umfangreiche Versuchsvorhaben im Auftrag des Bundeministeriums für Wirtschaft und Energie (bzw. seiner zuständigen Vorgänger) sowie zwei internationale Großprojekte im Auftrag der OECD-NEA durchgeführt. Die Versuchsergebnisse wurden international intensiv für die Validierung und Weiterentwicklung von Lumped-Parameter (LP)- und Computational Fluid Dynamics (CFD)-Codes genutzt. Beispiele für Code Benchmark Exercises, die mit Hilfe der THAI-Versuchsdaten durchgeführt wurden sind: Wasserstoff-Verteilungs Experiment (ISP-47 und OECD-NEA THAI Code Benchmark), Wasserstoff-Deflagrations Experiment (ISP-49), PAR-Wasserstoff-Beseitigungs Experiment (OECD-NEA THAI-2 Code Benchmark), Iod-Wechselwirkung mit Oberflächen, Iod-Massentransfer und Iod-Verhalten in der Mehrraum-Geometrie (EU-SARNET und EU-SARNET 2), sowie mehrere Thermohydraulik-Versuche (Deutsches CFD-Netzwerk). Im Folgenden wird ein Überblick über die THAI-Experimente und ihre Bedeutung für die Analyse der Vorgänge im Sicherheitsbehälter bei schweren Unfällen gegeben.
References
1 Gupta, S.; Schmidt, E.; von Laufenberg, B.; Freitag, M.; Poss, G.; Funke, F.; Weber, G.: THAI test facility for experimental research on hydrogen and fission product behaviour in light water reactor containments. Nuclear Engineering and Design294 (2015) 18310.1016/j.nucengdes.2015.09.013Search in Google Scholar
© 2016, Carl Hanser Verlag, München
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- Contents/Inhalt
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- Summaries/Kurzfassungen
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- Editorial
- Selected contributions from 1th Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
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- Scientific codes developed and used at GRS – Nuclear simulation chain
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- Validation of system codes for plant application on selected experiments
- Progress of Experimental Research on Nuclear Safety in NPIC
- Severe accident research activities at Helmholtz-Zentrum Dresden-Rossendorf (HZDR)
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Selected contributions from 1th Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
- Technical Contributions/Fachbeiträge
- Scientific codes developed and used at GRS – Nuclear simulation chain
- Challenges on innovations of newly-developed safety analysis codes
- Validation of system codes for plant application on selected experiments
- Progress of Experimental Research on Nuclear Safety in NPIC
- Severe accident research activities at Helmholtz-Zentrum Dresden-Rossendorf (HZDR)
- THAI experimental programme for containment safety assessment under severe accident conditions
- A spray cooling technique for spent fuel assembly stored in pool
- KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors
- Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors
- 10.3139/124.110680
- Validation of the ATHLET-SC code by trans-critical transient data
- Qualification of CFD-models for multiphase flows
- The reactor dynamics code DYN3D
- Critical flow phenomena and modeling in advanced nuclear safety technology
- 10.3139/124.110682
- Safety and security aspects in design of digital safety I&C in nuclear power plants
- Thermohydraulic safety issues for liquid metal cooled systems
- Design and safety analysis of the helium cooled solid breeder blanket for CFETR
- Qualification of pebble fuel for HTGRs
- High temperature reactors for cogeneration applications
