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Liquid-salt-cooled Reactor Start-up with Natural Circulation

Emilien Gros ; Georgia Institute of Technology, Nuclear and Radiological Engineering 770 State Street, NW, Atlanta, GA 30332-0745, USA
Bojan Petrović ; Georgia Institute of Technology, Nuclear and Radiological Engineering 770 State Street, NW, Atlanta, GA 30332-0745, USA
Davor Grgić ; Faculty of Electrical Engineering and Computing University of Zagreb (Croatia)

Puni tekst: engleski, pdf (1 MB) str. 0-0 preuzimanja: 73* citiraj
APA 6th Edition
Gros, E., Petrović, B. i Grgić, D. (2013). Liquid-salt-cooled Reactor Start-up with Natural Circulation. Journal of Energy, 62 (1-4), 0-0. Preuzeto s https://hrcak.srce.hr/199049
MLA 8th Edition
Gros, Emilien, et al. "Liquid-salt-cooled Reactor Start-up with Natural Circulation." Journal of Energy, vol. 62, br. 1-4, 2013, str. 0-0. https://hrcak.srce.hr/199049. Citirano 28.05.2020.
Chicago 17th Edition
Gros, Emilien, Bojan Petrović i Davor Grgić. "Liquid-salt-cooled Reactor Start-up with Natural Circulation." Journal of Energy 62, br. 1-4 (2013): 0-0. https://hrcak.srce.hr/199049
Harvard
Gros, E., Petrović, B., i Grgić, D. (2013). 'Liquid-salt-cooled Reactor Start-up with Natural Circulation', Journal of Energy, 62(1-4), str. 0-0. Preuzeto s: https://hrcak.srce.hr/199049 (Datum pristupa: 28.05.2020.)
Vancouver
Gros E, Petrović B, Grgić D. Liquid-salt-cooled Reactor Start-up with Natural Circulation. Journal of Energy [Internet]. 2013 [pristupljeno 28.05.2020.];62(1-4):0-0. Dostupno na: https://hrcak.srce.hr/199049
IEEE
E. Gros, B. Petrović i D. Grgić, "Liquid-salt-cooled Reactor Start-up with Natural Circulation", Journal of Energy, vol.62, br. 1-4, str. 0-0, 2013. [Online]. Dostupno na: https://hrcak.srce.hr/199049. [Citirano: 28.05.2020.]

Sažetak
The Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) was modeled using
the neutronics analysis code SCALE6.0 and the thermal-hydraulics and kinetics modeling code
RELAP5-3D with objective to devise, analyze, and evaluate the feasibility and stability of a start-up
procedure for this reactor using natural circulation of the coolant and under the Loss Of Offsite
Power (LOOP) conditions.
This Generation IV reactor design has been initially developed by Oak Ridge National
Laboratory and studied by researchers worldwide for almost a decade. While neutronics and
thermal-hydraulics analyses have been previously performed to show the performance of the reactor
during normal operation and for shutdown scenarios, no study has heretofore been published to
examine the active or passive start-up of the reactor.
The fuel temperature (Doppler) and coolant density coefficient of reactivity of the LSVHTR
were examined using the CSAS6 module of the SCALE6.0 code. Negative Doppler and
coolant density feedback coefficients were calculated.
Two initial RELAP5 simulations were performed to obtain the steady-state conditions of the
model and to predict the changes of the thermal-hydraulic parameters during the shutdown of the
reactor. Next, a series of step reactivity additions to the core were simulated to determine how much
reactivity can be inserted without jeopardizing the safety and stability of the core. Finally, a start-up
procedure was developed, and the restart of the reactor with natural convection of the coolant was
simulated. The results of the simulations demonstrated the potential for natural circulation start-up
of the LS-VHTR.

Hrčak ID: 199049

URI
https://hrcak.srce.hr/199049

Posjeta: 97 *