Study of 60Co as gamma source in backscatter gamma densitometers
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R. Gholipour Peyvandi
, S. Z. Islami Rad , A. Taheri , S. Rahmanzadeh Tootkaleh and M. Askari Lehdarboni
Abstract
In this work the performance of backscatter gamma densitometer is studied using 60Co as gamma source. The ability of the densitometer to determine the liquid's interfaces in multi-phase flows was assessed. The aim mainly was to investigate the possibility of using 60Co in this system. Furthermore, a comparison between 60Co and was done. The obtained results indicate that 60Co can be advantageous in this regard.
Kurzfassung
In diesem Beitrag wird die Leistungsfähigkeit eines Gamma-Densitometers mit 60Co als Strahlenquelle untersucht. Die Fähigkeit des Densitometers, Flüssigkeitsgrenzflächen bei Multiphasenströmungen zu bestimmen, wurde bewertet. Hauptziel war die Untersuchung der Verwendung von 60Co als Strahlenquelle in diesem System. Des Weiteren wurde ein Vergleich zwischen 60Co und 137Cs durchgeführt. Die erhaltenen Ergebnisse zeigen, dass die Verwendung von 60Co Vorteile haben kann.
References
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© 2015, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved data evaluation methodology for energy ranges with missing experimental data
- Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
- Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
- The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
- Development of a hydrogen diffusion gothic model of MARK III-containment
- Analysis of safety parameters for the MINERVE reactor
- Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
- Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
- Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
- Study of 60Co as gamma source in backscatter gamma densitometers
- Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
- Technical Notes
- Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions