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dc.contributor.authorMorita, Koji
dc.contributor.authorLiu, Wei
dc.contributor.authorArima, Tatsumi
dc.contributor.authorArita, Yuji
dc.contributor.authorSato, Isamu
dc.contributor.authorMatsuura, Haruaki
dc.contributor.authorSekio, Yoshihiro
dc.contributor.authorSagara, Hiroshi
dc.contributor.authorKawashima, Masatoshi
dc.date.accessioned2023-11-29T19:35:53Z
dc.date.available2023-11-29T19:35:53Z
dc.date.copyright3/14/2023 12:00:00 AM
dc.date.issued3/14/2023 12:00:00 AM
dc.date.issued2023-03-14
dc.identifier.issn2332-8983
dc.identifier.otherners_009_04_041302.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4294884
dc.description.abstractA new subassembly type passive reactor shutdown device is proposed to expand the diversity and robustness of core disruptive accident prevention measures for sodium-cooled fast reactors (SFRs). The device contains pins with a fuel material that is in a solid state during normal operation but melts and fluidizes during an unprotected loss of flow (ULOF) or unprotected transient overpower (UTOP) accident. By rapidly transferring the liquefied device fuel into the lower plenum region of the pins via gravitation alone, the device passively provides high negative reactivity to the core. This study evaluated the nuclear and thermal properties of the device subassembly with metallic fuel to determine the device specifications for proper device operation during ULOF and UTOP accidents. The results of the transient analysis of the ULOF initiating phase in a 750-MWel-class mixed-oxide-fueled SFR core confirmed that a conventional homogeneous core maintains stable cooling of the core before coolant boiling in the driver fuel subassemblies. In contrast, the negative reactivity required to terminate the event by device operation was slightly higher in the low sodium void reactivity core than in the conventional homogeneous core.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleDevelopment of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
dc.typeJournal Paper
dc.journal.volume9
dc.journal.issue4
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4056854
dc.journal.fristpage41102-1
dc.journal.lastpage41102-9
dc.page9
dc.treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 004
dc.contenttypeFulltext


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