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    Interactions Between Molten Sodium and Standard Pipe Insulation 

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003:;page 30901-1
    Author(s): LaBrier, Daniel; Harley, Jordan; Robbins, Morgan
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Safety system design and implementation are critical to the operation of any nuclear plant. For sodium-cooled nuclear reactors, hazards external to the reactor core are present in the form of molten sodium that leaks through ...
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    Experimental Study of Aqueous Chemical Trisodium Phosphate-Buffered Environment Under Post-LOCA Conditions With Head Loss Measurements 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002:;page 21002
    Author(s): Ali, Amir; LaBrier, Daniel; Howe, Kerry J.; Blandford, Edward D.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: An integrated chemical effects test (ICET) was designed and executed to investigate the corrosion of materials in a hypothetical post-loss of coolant accident (LOCA) environment for pressurized water reactors (PWRs) and ...
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    Integrated Chemical Effects Head Loss Experiments Using Multiconstituent Fibrous Debris Beds 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001:;page 11006
    Author(s): LaBrier, Daniel; Ali, Amir; Howe, Kerry J.; Blandford, Edward D.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The chemical head loss experiment (CHLE) program has been designed to acquire realistic material release and product formation in containment under post-loss of coolant accident (LOCA) conditions and their impact on the ...
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