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    Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001::page 11012
    Author:
    Sukarman,
    ,
    Yamaji, Akifumi
    ,
    Someya, Takayuki
    DOI: 10.1115/1.4037719
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The authors look for an attractive light water reactor (LWR) concept, which achieves high breeding performance with respect to the compound system doubling time (CSDT). In the preceding study, a high breeding fast reactor concept, cooled by supercritical pressure light water (Super FBR), was developed using tightly packed fuel assembly (TPFA) concept, in which fuel rods were arranged in a hexagonal lattice and packed by contacting each other. However, the designed concept had characteristics, which had to be improved, such as low power density (7.4 kW/m), large core pressure loss (1.02 MPa), low discharge burnup (core average: 8 GWd/t), and low coolant temperature rise in the core (38 °C). The aim of this study is to clarify the main issues associated with improvement of the Super FBR with respect to these design parameters and to show the improved design. The core design is carried out by fully coupled three-dimensional neutronics and single-channel thermal-hydraulic core calculations. The design criteria are negative void reactivity, maximum linear heat generation rate (MLHGR) of 39 kW/m, and maximum cladding surface temperature (MCST) of 650 °C for advanced stainless steel. The results show that significant improvement is possible with respect to the core thermal-hydraulic characteristics with minimal deterioration of CSDT by replacing TPFA with the commonly acknowledged hexagonal tight lattice fuel assembly (TLFA). Further design studies are necessary to improve the core enthalpy rise by reducing the radial power swing and power peaking.
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      Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water

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    https://yetl.yabesh.ir/yetl1/handle/yetl/4252614
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorSukarman,
    contributor authorYamaji, Akifumi
    contributor authorSomeya, Takayuki
    date accessioned2019-02-28T11:05:43Z
    date available2019-02-28T11:05:43Z
    date copyright12/4/2017 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_01_011012.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252614
    description abstractThe authors look for an attractive light water reactor (LWR) concept, which achieves high breeding performance with respect to the compound system doubling time (CSDT). In the preceding study, a high breeding fast reactor concept, cooled by supercritical pressure light water (Super FBR), was developed using tightly packed fuel assembly (TPFA) concept, in which fuel rods were arranged in a hexagonal lattice and packed by contacting each other. However, the designed concept had characteristics, which had to be improved, such as low power density (7.4 kW/m), large core pressure loss (1.02 MPa), low discharge burnup (core average: 8 GWd/t), and low coolant temperature rise in the core (38 °C). The aim of this study is to clarify the main issues associated with improvement of the Super FBR with respect to these design parameters and to show the improved design. The core design is carried out by fully coupled three-dimensional neutronics and single-channel thermal-hydraulic core calculations. The design criteria are negative void reactivity, maximum linear heat generation rate (MLHGR) of 39 kW/m, and maximum cladding surface temperature (MCST) of 650 °C for advanced stainless steel. The results show that significant improvement is possible with respect to the core thermal-hydraulic characteristics with minimal deterioration of CSDT by replacing TPFA with the commonly acknowledged hexagonal tight lattice fuel assembly (TLFA). Further design studies are necessary to improve the core enthalpy rise by reducing the radial power swing and power peaking.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleImproved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water
    typeJournal Paper
    journal volume4
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4037719
    journal fristpage11012
    journal lastpage011012-8
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001
    contenttypeFulltext
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