Ionut Gheorghe Anghel
Royal Institute of Technology
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2010 14th International Heat Transfer Conference, Volume 2 | 2010
Ionut Gheorghe Anghel; Henryk Anglart; Stellan Hedberg
The purpose of this paper is to present the experimental setup, experimental method and results of the recent post-dryout heat transfer investigations in an annulus with pin spacers. The experiments were performed in the thermal-hydraulic laboratory at the Royal Institute of Technology (KTH), Stockholm, Sweden. The experimental facility has an annular test section which consists of two double-heated concentric tubes manufactured of Inconel 600. Five levels of pin spacers were installed along the test section to keep the rod and the tube equidistant during experiments. The experimental matrix includes measurements of wall temperature distributions for single phase and two-phase flows, for both convective boiling and post-dryout heat transfer regimes. The influence of variations in mass flux (500–1500) kg/(m2 s) and inlet subcooling 10 and 40 K at system pressure of 7 MPa were investigated. The experimental results indicate that post dryout heat transfer is influenced by the pin spacers. In particular it has been observed that the dry patch appearing in the test section can be quenched downstream of the pins-spacer. The current results provide additional experimental database which can be used for validation of post-dryout heat transfer models including the flow obstacle effects.Copyright
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance | 2009
Ionut Gheorghe Anghel; Henryk Anglart; Stellan Hedberg; Stefan Rydström
This paper describes the experimental setup, instrumentation and procedures which have been developed in the thermal-hydraulic laboratory at the Royal Institute of Technology (KTH), Stockholm, Swed ...
Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14; Miami, FL; United States | 2006
Ionut Gheorghe Anghel; Henryk Anglart
The present paper presents results of the TRACE code assessment against post dryout experimental data obtained in tubes and annuli. The investigations have been focused on the experiments carried out at 70 bar pressure, 10 K inlet subcooling and the mass flux variation between 500–2000 kg/(m2 s). Various axial power distributions (uniform, inlet peaked, middle peaked, and outlet peaked) have been used in the tube geometry. Uniform power distributions, with various ratios between the inner and the outer power have been used in the annulus geometry. The validation results indicated that the discrepancies between measured and calculated data are in a range of ±20%. In addition a sensitivity study has been performed in which the influence of several parameters (including cell size and boundary conditions) on computational results have been investigated.Copyright
International Journal of Heat and Mass Transfer | 2012
Ionut Gheorghe Anghel; Henryk Anglart
Journal of Power of Technologies | 2014
Ionut Gheorghe Anghel; Henryk Anglart
Nuclear Engineering and Design | 2012
Ionut Gheorghe Anghel; Henryk Anglart; Stellan Hedberg
Nuclear Engineering and Design | 2014
Ionut Gheorghe Anghel; Henryk Anglart
International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15); 12-17 May, 2013. Pisa, Italy | 2013
Ionut Gheorghe Anghel; Henryk Anglart
Archive | 2011
Ionut Gheorghe Anghel; Henryk Anglart
NURETH-14. Toronto, Canada. Sept. 25-30 2011 | 2011
Ionut Gheorghe Anghel; Henryk Anglart