Unprotected loss of flow accident (ULOF) is the most typical severe accident in sodium cooled fast reactor, which is focused by scholars civil and abroad. Metallic fuel has different safety characteristics with the oxide fuel as the important development direction of future sodium fast reactor, accident analysis of which is also a research focus at home and abroad. This paper bases on one Cooperation Research Project proposed by ANL and organized by IAEA, analyses the Shut-down Removal Test-45R of the metallic fuel sodium cooled fast reactor EBR-II in the US with SAS4A code, to research the transient characteristics of it in ULOF accident. Studies have shown that, metallic fuel sodium cooled fast reactor has very good inherent safety performance, which can reduce the reactor power in ULOF accident through the negative feedback itself.
The Study About the Transient Characteristics of Metallic Fuel Sodium Cooled Fast Reactor in the Unprotected Loss of Flow Accident Based on the SAS4A Code
Qiao, P, & Hu, W. "The Study About the Transient Characteristics of Metallic Fuel Sodium Cooled Fast Reactor in the Unprotected Loss of Flow Accident Based on the SAS4A Code." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A001. ASME. https://doi.org/10.1115/ICONE25-66018
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