Thermohydraulic safety issues for liquid metal cooled systems
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G. Gerbeth
Abstract
In this paper recent developments of various techniques for single-phase and two-phase flow measurements with relevance to liquid metal cooled systems will be presented. Further, the status of the DRESDYN platform for large-scale experiments with liquid sodium is sketched.
Kurzfassung
In diesem Beitrag wird über die jüngsten Entwicklungen auf dem Gebiet der Strömungsmesstechnik für einphasige und zweiphasige Systeme, welche für flüssigmetallgekühlte Systeme relevant sind, berichtet. Skizziert wird des Weiteren der gegenwärtige Stand der DRESDYN-Plattform für großskalige Experiment mit flüssigem Natrium.
References
1 Tenchine, D.: Some thermal hydraulic challenges in sodium cooled fast reactors. Nucl. Eng. Des.240 (2010) 119510.1016/j.nucengdes.2010.01.006Search in Google Scholar
2 Merk, B. et al.: Progress in reliability of fast reactor operation and new trends to increased inherent safety. Appl. Energy147 (2015) 10410.1016/j.apenergy.2015.02.023Search in Google Scholar
3 Abderrahim, H. H. et al.: MYRRHA – A multi-purpose fast spectrum research reactor. Energy Conv. Manag.63 (2012) 410.1016/j.enconman.2012.02.025Search in Google Scholar
4 Eckert, S. et al.: Some recent developments in the field of measuring techniques and instrumentation for liquid metal flows. J. Nucl. Sci. Techn.48 (2011) 49010.1080/18811248.2011.9711724Search in Google Scholar
5 Buchenau, D. et al.: Measurement technique developments for LBE flows. J. Nucl. Mat.415 (2011) 39610.1016/j.jnucmat.2011.04.026Search in Google Scholar
6 Stefani, F. et al.: DRESDYN – A new facility for MHD experiments with liquid sodium. Magnetohydrodynamics48 (2012) 10310.22364/mhd.48.1.13Search in Google Scholar
7 Priede, J. et al.: A contactless electromagnetic flowrate sensor based on phase-shift measurements, Meas. Sci. Techn.22 (2011) 05540210.1088/0957-0233/22/5/055402Search in Google Scholar
8 Forbriger, J., Stefani, F.: Transient eddy current flow metering. Meas. Sci. Technol.26 (2015) 10530310.1088/0957-0233/26/10/105303Search in Google Scholar
9 Eckert, S., Gerbeth, G.: Velocity measurements in liquid sodium by means of ultrasound Doppler velocimetry. Exp. Fluids32 (2002) 54210.1007/s00348-001-0380-9Search in Google Scholar
10 Eckert, S. et al.: Velocity measurements at high temperatures by ultrasound Doppler velocimetry using an acoustic wave guide. Exp. Fluids35 (2003) 38110.1007/s00348-003-0606-0Search in Google Scholar
11 Stefani, F. et al.: Contactless inductive flow tomography. Phys. Rev. E70 (2004) 05630610.1103/PhysRevE.70.056306Search in Google Scholar PubMed
12 Cramer, A. et al.: Experimental study on the sensitivity and accuracy of electric potential local flow measurements. Flow Meas. Instrum.17 (2006) 110.1016/j.flowmeasinst.2005.08.006Search in Google Scholar
13 Terzija, N. et al.: Electromagnetic inspection of a two-phase flow of GaInSn and argon. Flow Meas. Instr.22 (2011) 1010.1016/j.flowmeasinst.2010.10.003Search in Google Scholar
14 Vogt, T. et al.: Detection of gas entrainment into liquid metals. Nucl. Eng. Des.294 (2015) 1610.1016/j.nucengdes.2015.07.072Search in Google Scholar
15 Altstadt, E. et al.: A photo-neutron source for time-of-flight measurements at the radiation source ELBE. Ann. Nucl. Ener.35 (2007) 3610.1016/j.anucene.2006.11.005Search in Google Scholar
© 2016, Carl Hanser Verlag, München
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
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- 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
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
