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    Influence of Accident-Tolerant Fuel With Steel Cladding for Sustainable Heat Transfer in the Reactor Core of VVER-1200

    Source: ASME Open Journal of Engineering:;2022:;volume( 001 )::page 11023
    Author:
    Sanglap, MD Tanzib Ehsan;Shahriar, Sazidur Rahman
    DOI: 10.1115/1.4054476
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Since the events at the Fukushima–Daiichi nuclear power plant, there has been increased interest in developing accident tolerant fuel (ATF) to avoid accidents for light water reactors where Uranium-Silicide-based fuel has an excellent field to minimize the hydrogen hazards. Similarly, steel cladding is at the center of attraction for researchers nowadays. In this research, the feasibility of using Uranium-Silicides (i.e., U3Si, U3Si2, and U3Si5) combined with different types of austenitic steel (i.e., AISI) was investigated to improve the safety performance. A three-dimensional (3D) computational fluid dynamics (CFD)-coded star ccm+ model was used to assess heat transfer performance in the hexagonal fuel assembly of a supercritical water-cooled reactor VVER-1200. Utilizing the computational environment of star ccm+, the test analysis was conducted for a portion of fuel height using the realizable K-Epsilon Two-Layer Wall turbulence model. This analysis showed that the combination of U3Si2 fuel with AISI-348 cladding got superiority over other ATF-AISI fuel-claddings assemblies to use in the reactor core of VVER-1200 because of their lower central fuel temperature value with good mechanical and thermal advantages. This work also derived an empirical heat transfer coefficient equation to guide the relevant future investigations on the thermal analysis of the core.
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      Influence of Accident-Tolerant Fuel With Steel Cladding for Sustainable Heat Transfer in the Reactor Core of VVER-1200

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4288096
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    contributor authorSanglap, MD Tanzib Ehsan;Shahriar, Sazidur Rahman
    date accessioned2022-12-27T23:12:06Z
    date available2022-12-27T23:12:06Z
    date copyright5/17/2022 12:00:00 AM
    date issued2022
    identifier issn2770-3495
    identifier otheraoje_1_011023.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4288096
    description abstractSince the events at the Fukushima–Daiichi nuclear power plant, there has been increased interest in developing accident tolerant fuel (ATF) to avoid accidents for light water reactors where Uranium-Silicide-based fuel has an excellent field to minimize the hydrogen hazards. Similarly, steel cladding is at the center of attraction for researchers nowadays. In this research, the feasibility of using Uranium-Silicides (i.e., U3Si, U3Si2, and U3Si5) combined with different types of austenitic steel (i.e., AISI) was investigated to improve the safety performance. A three-dimensional (3D) computational fluid dynamics (CFD)-coded star ccm+ model was used to assess heat transfer performance in the hexagonal fuel assembly of a supercritical water-cooled reactor VVER-1200. Utilizing the computational environment of star ccm+, the test analysis was conducted for a portion of fuel height using the realizable K-Epsilon Two-Layer Wall turbulence model. This analysis showed that the combination of U3Si2 fuel with AISI-348 cladding got superiority over other ATF-AISI fuel-claddings assemblies to use in the reactor core of VVER-1200 because of their lower central fuel temperature value with good mechanical and thermal advantages. This work also derived an empirical heat transfer coefficient equation to guide the relevant future investigations on the thermal analysis of the core.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleInfluence of Accident-Tolerant Fuel With Steel Cladding for Sustainable Heat Transfer in the Reactor Core of VVER-1200
    typeJournal Paper
    journal volume1
    journal titleASME Open Journal of Engineering
    identifier doi10.1115/1.4054476
    journal fristpage11023
    journal lastpage11023_10
    page10
    treeASME Open Journal of Engineering:;2022:;volume( 001 )
    contenttypeFulltext
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