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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:
    LaBrier, Daniel
    ,
    Harley, Jordan
    ,
    Robbins, Morgan
    DOI: 10.1115/1.4062798
    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 degraded piping structures. These structures are often clad in high-temperature insulation to preserve the heat needed to keep the sodium molten in the piping. While large sodium leaks are quite noticeable and often result in hazardous fire situations, small leaks of molten sodium are often masked by the shroud of insulation until a large pool of material has collected outside of the failed pipe. This study concentrated on the physical and chemical interactions between molten sodium and standard fiberglass insulation in temperatures ranging from 100 °C to 500 °C. The degradation of the insulation material begins with the volatilization of the organic binder around 250 °C, thereafter the insulation deteriorates at an advanced rate in areas that are in direct contact with the sodium. Chemical profile data were collected for a variety of sample locations that were in contact with the molten sodium, with only a slight increase in the amount of sodium present that can be attributed to the external sodium source. In this way, the molten sodium chemically reacts with the insulation, which accelerates the degradation of the insulation in locations where the sodium is in direct contact with the insulation. These reactions are enhanced by the temperature of the sodium.
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      Interactions Between Molten Sodium and Standard Pipe Insulation

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4295748
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    contributor authorLaBrier, Daniel
    contributor authorHarley, Jordan
    contributor authorRobbins, Morgan
    date accessioned2024-04-24T22:43:13Z
    date available2024-04-24T22:43:13Z
    date copyright3/8/2024 12:00:00 AM
    date issued2024
    identifier issn2332-8983
    identifier otherners_010_03_030901.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4295748
    description abstractSafety 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 degraded piping structures. These structures are often clad in high-temperature insulation to preserve the heat needed to keep the sodium molten in the piping. While large sodium leaks are quite noticeable and often result in hazardous fire situations, small leaks of molten sodium are often masked by the shroud of insulation until a large pool of material has collected outside of the failed pipe. This study concentrated on the physical and chemical interactions between molten sodium and standard fiberglass insulation in temperatures ranging from 100 °C to 500 °C. The degradation of the insulation material begins with the volatilization of the organic binder around 250 °C, thereafter the insulation deteriorates at an advanced rate in areas that are in direct contact with the sodium. Chemical profile data were collected for a variety of sample locations that were in contact with the molten sodium, with only a slight increase in the amount of sodium present that can be attributed to the external sodium source. In this way, the molten sodium chemically reacts with the insulation, which accelerates the degradation of the insulation in locations where the sodium is in direct contact with the insulation. These reactions are enhanced by the temperature of the sodium.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleInteractions Between Molten Sodium and Standard Pipe Insulation
    typeJournal Paper
    journal volume10
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4062798
    journal fristpage30901-1
    journal lastpage30901-8
    page8
    treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 003
    contenttypeFulltext
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