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    Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 002::page 21501
    Author:
    Sasaki, Ryotaro;Yamaji, Akifumi;Uchimura, Kyota
    DOI: 10.1115/1.4053827
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The small modular reactor (SMR) class core design concept of once-through supercritical light water-cooled reactor (SCWR) with fast neutron spectrum (super fast reactor (FR)) is being developed at Waseda University. For the 300 MWel class design, complete core meltdown may need to be considered in case of a severe accident. This study proposes the new in-vessel retention (IVR) concept of the SMR class super FR (super FR-IVR), which can avoid recriticality even if the whole core relocates to the lower plenum of the reactor pressure vessel (RPV). The core characteristics with a given set of design specifications and criteria are evaluated based on fully coupled neutronics and thermal-hydraulics core burnup calculations. The debris criticality is evaluated based on Monte Carlo based method to consider the RPV lower plenum and debris configurations. The relationships between the 300 MWel class core design with the inner vessel diameter of 2.32 m and the IVR design are revealed. By reducing the operation cycle length from 720 days to 360 days and increasing the core inlet temperature from 280 °C to 370 °C, the required IVR submergence level could be reduced from 2.18 m to 1.38 m, assuming that the debris bed (melt pool) is homogeneous. However, when fully stratified debris configurations are assumed, the required disperser height and the corresponding IVR submergence level may increase to about 2.70 m.
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      Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4288382
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    contributor authorSasaki, Ryotaro;Yamaji, Akifumi;Uchimura, Kyota
    date accessioned2022-12-27T23:19:31Z
    date available2022-12-27T23:19:31Z
    date copyright6/15/2022 12:00:00 AM
    date issued2022
    identifier issn2332-8983
    identifier otherners_009_02_021501.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4288382
    description abstractThe small modular reactor (SMR) class core design concept of once-through supercritical light water-cooled reactor (SCWR) with fast neutron spectrum (super fast reactor (FR)) is being developed at Waseda University. For the 300 MWel class design, complete core meltdown may need to be considered in case of a severe accident. This study proposes the new in-vessel retention (IVR) concept of the SMR class super FR (super FR-IVR), which can avoid recriticality even if the whole core relocates to the lower plenum of the reactor pressure vessel (RPV). The core characteristics with a given set of design specifications and criteria are evaluated based on fully coupled neutronics and thermal-hydraulics core burnup calculations. The debris criticality is evaluated based on Monte Carlo based method to consider the RPV lower plenum and debris configurations. The relationships between the 300 MWel class core design with the inner vessel diameter of 2.32 m and the IVR design are revealed. By reducing the operation cycle length from 720 days to 360 days and increasing the core inlet temperature from 280 °C to 370 °C, the required IVR submergence level could be reduced from 2.18 m to 1.38 m, assuming that the debris bed (melt pool) is homogeneous. However, when fully stratified debris configurations are assumed, the required disperser height and the corresponding IVR submergence level may increase to about 2.70 m.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleDesign Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
    typeJournal Paper
    journal volume9
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4053827
    journal fristpage21501
    journal lastpage21501_7
    page7
    treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 002
    contenttypeFulltext
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