Performance evaluation of the Floating Absorber for Safety at Transient (FAST) in the innovative Sodium-cooled Fast Reactor (iSFR) under a single control rod withdrawal accident

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The Floating Absorber for Safety at Transient (FAST) is a safety device used in the innovative Sodium-cooled Fast Reactor (iSFR). The FAST insert negative reactivity under transient or accident conditions. However, behavior of the FAST is still unclear under transient conditions. Therefore, the existing Floating Absorber for Safety at Transient Analysis Code (FASTAC) is improved to analyze the FAST movement by considering the reactivity and temperature distribution within the reactor core. The current FAST system is simulated under a single control rod withdrawal accident condition. In this investigation, the reactor thermal power does not return to its initial thermal power even if the FAST inserts negative reactivity. Only a 9 K of coolant temperature margin, in the hottest fuel assembly at EOL, can lead to unnecessary insertion of the negative reactivity. On the other hand, the FASTs cannot contribute to controlling the reactivity when normalized radial power is less than 0.889 at BOL and 0.972 at EOL. These simulation results suggest that the current FAST design needs to be optimized depending on its installed location. Meanwhile, the FAST system keeps the fuel, cladding and coolant temperatures below their limit temperatures with given conditions.
Publisher
KOREAN NUCLEAR SOC
Issue Date
2020-06
Language
English
Article Type
Article
Citation

NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.6, pp.1110 - 1119

ISSN
1738-5733
DOI
10.1016/j.net.2019.11.011
URI
http://hdl.handle.net/10203/274696
Appears in Collection
NE-Journal Papers(저널논문)
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