Abstract
Innovative Research Reactor 50 MW (RRI-50) is a conceptual design of an Indonesia's high-power innovative research reactor, which is designed to produce a maximum neutron flux as high as 1.0 × 1015 n/cm2 s and thermal neutron flux of 5.0 × 1014 n/cm2 s. In this study, the design basis accident slow reactivity insertion is carried out. Reactivity insertion accident (RIA) caused by the inadvertent withdrawal of all fuel rod at normal rate is simulated by using PARET-ANL transient code. In the simulation accident is assumed to occur when the reactor is in operation at high power and at low power level. During transient, the fuel rods are assumed to be in the most effective positions with insertion rate of 0.049 $/s. This reactivity worth will give effect only if the fuel rod interlock system is failed to function properly and the operator action does not follow the standard operation procedure. The analysis results show that the reactor experiences scram when it reaches its protected power at high power level of 110 % (55 MW) at period of 5 s and at low power level of 3 MW at period of 120 s, and there is sufficient safety margin for the anticipated RIA caused by reactivity feedback.
Kurzfassung
Der Forschungsreaktor 50 MW (RRI-50) ist ein Konzeptentwurf für einen innovativen indonesischen Hochleistungs-Forschungsreaktor, der darauf ausgelegt ist, einen maximalen Neutronenfluss von bis zu 1,0 × 1 015 n/cm2 s und einen thermischen Neutronenfluss von 5,0 × 1 014 n/cm2 s zu erzeugen. In dieser Studie wird eine Analyse des Auslegungsstörfalls unbeabsichtigten Kontrollstabauswurfs mit Hilfe des PARET-ANL-Transientencodes durchgeführt. In der Simulation wird davon ausgegangen, dass dieses Ereignis auftreten kann, wenn der Reaktor mit hoher Leistung und mit niedriger Leistung in Betrieb ist. Während der Transientenphase wird angenommen, dass sich die Brennstäbe in den effektivsten Positionen mit einer Rate von 0,049 $/s befinden. Diese Reaktivität wirkt sich nur dann aus, wenn das Brennstabverriegelungssystem nicht ordnungsgemäß funktioniert und die Bedienung nicht dem normalen Betriebsablauf folgt. Die Analyseergebnisse zeigen, dass sich der Reaktor im Fall der einer hohen Leistung bei 110 % (55 MW) nach 5 Sekunden und im Fall der niedrigen Leistung von 3 MW nach 120 Sekunden abschaltet. In beiden Fällen ist durch die Rückkopplung der Reaktivität eine ausreichende Sicherheitsmarge vorhanden.
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