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    Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 003:;page 31401-1
    Author(s): Kikuchi, Norihiro; Imai, Yasutomo; Yoshikawa, Ryuji; Doda, Norihiro; Tanaka, Masaaki
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In the design study of an advanced sodium-cooled fast reactor (advanced-SFR) in Japan Atomic Energy Agency (JAEA), the use of a specific fuel assembly (FA) with an inner duct structure called fuel assembly with an inner ...
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    Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 002:;page 21001
    Author(s): Kikuchi, Norihiro; Imai, Yasutomo; Yoshikawa, Ryuji; Doda, Norihiro; Tanaka, Masaaki; Ohshima, Hiroyuki
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In the design study of advanced loop-type sodium-cooled fast reactor in Japan, a specific fuel assembly (FA) called FA with inner duct structure (FAIDUS) is expected to enhance reactor safety during a core-disruptive ...
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    Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 002:;page 21001
    Author(s): Kikuchi, Norihiro; Imai, Yasutomo; Yoshikawa, Ryuji; Doda, Norihiro; Tanaka, Masaaki; Ohshima, Hiroyuki
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: In the design study of advanced loop-type sodium-cooled fast reactor in Japan, a specific fuel assembly (FA) called FA with inner duct structure (FAIDUS) is expected to enhance reactor safety during a core-disruptive ...
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