Improved core design of a high breeding fast reactor cooled by supercritical pressure light water

Takayuki Someya, Akifumi Yamaji, Sukarman

    Research output: Contribution to journalArticle

    1 Citation (Scopus)

    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.

    Original languageEnglish
    Article number021002
    JournalJournal of Nuclear Engineering and Radiation Science
    Volume4
    Issue number1
    DOIs
    Publication statusPublished - 2018 Jan 1

    Fingerprint

    supercritical pressures
    light water
    Fast reactors
    reactors
    Water
    assembly
    Hydraulics
    hydraulics
    Light water reactors
    Heat generation
    light water reactors
    Coolants
    Deterioration
    Enthalpy
    heat generation
    Stainless steel
    coolants
    deterioration
    surface temperature
    Temperature

    Keywords

    • Compound system doubling time (CSDT)
    • Fast breeder reactor (FBR)
    • Supercritical light water reactor
    • Tight lattice fuel assembly (TLFA)
    • Tightly packed fuel assembly (TPFA)

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering
    • Radiation

    Cite this

    Improved core design of a high breeding fast reactor cooled by supercritical pressure light water. / Someya, Takayuki; Yamaji, Akifumi; Sukarman.

    In: Journal of Nuclear Engineering and Radiation Science, Vol. 4, No. 1, 021002, 01.01.2018.

    Research output: Contribution to journalArticle

    @article{b36ad4afcce84a328461df42280a55a2,
    title = "Improved core design of a high breeding fast reactor cooled by supercritical pressure light water",
    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.",
    keywords = "Compound system doubling time (CSDT), Fast breeder reactor (FBR), Supercritical light water reactor, Tight lattice fuel assembly (TLFA), Tightly packed fuel assembly (TPFA)",
    author = "Takayuki Someya and Akifumi Yamaji and Sukarman",
    year = "2018",
    month = "1",
    day = "1",
    doi = "10.1115/1.4037719",
    language = "English",
    volume = "4",
    journal = "Journal of Nuclear Engineering and Radiation Science",
    issn = "2332-8983",
    publisher = "American Society of Mechanical Engineers(ASME)",
    number = "1",

    }

    TY - JOUR

    T1 - Improved core design of a high breeding fast reactor cooled by supercritical pressure light water

    AU - Someya, Takayuki

    AU - Yamaji, Akifumi

    AU - Sukarman,

    PY - 2018/1/1

    Y1 - 2018/1/1

    N2 - 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.

    AB - 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.

    KW - Compound system doubling time (CSDT)

    KW - Fast breeder reactor (FBR)

    KW - Supercritical light water reactor

    KW - Tight lattice fuel assembly (TLFA)

    KW - Tightly packed fuel assembly (TPFA)

    UR - http://www.scopus.com/inward/record.url?scp=85046258647&partnerID=8YFLogxK

    UR - http://www.scopus.com/inward/citedby.url?scp=85046258647&partnerID=8YFLogxK

    U2 - 10.1115/1.4037719

    DO - 10.1115/1.4037719

    M3 - Article

    AN - SCOPUS:85046258647

    VL - 4

    JO - Journal of Nuclear Engineering and Radiation Science

    JF - Journal of Nuclear Engineering and Radiation Science

    SN - 2332-8983

    IS - 1

    M1 - 021002

    ER -