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    Uranium-Molybdenum Alloy for Use in a Prompt-Burst Reactor

    Source: Journal of Fluids Engineering:;1965:;volume( 087 ):;issue: 004::page 865
    Author:
    F. Rienecker
    ,
    W. H. Moran
    DOI: 10.1115/1.3650831
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A large prompt-burst nuclear reactor, “Super Kukla,” required a core of material that would withstand unusually high stress levels resulting from rapid thermal expansion and inertia loads. An experimental investigation was undertaken to determine the properties of cast uranium—10 wt percent molybdenum alloy under static and dynamic conditions of loading at various temperatures for application in this reactor. Techniques were developed to cast, inspect by radiographic and ultrasonic means, machine, and nickel plate the material. Castings are in the form of rings, 30 in. OD, 18 in. ID, and 2 in. thick. Sound material with carbon content of less than 250 ppm was found to have a static yield strength of approximately 130,000 psi, ultimate strength of 133,000 psi, and elongation of 10 percent at room temperature. Sustained static loads of more than 40,000 psi in a normal atmosphere were found to induce a brittle fracture attributed to stress corrosion. Test specimens subjected to strain rates on the order of 20 in/in/sec withstood stresses of 200,000 psi in the gage region, but usually failed in the threaded ends.
    keyword(s): Alloys , molybdenum , Uranium , Stress , Temperature , Nickel , Machinery , Inertia (Mechanics) , Thermal expansion , Gages , Sound , Molybdenum alloys , Stress corrosion cracking , Carbon , Elongation , Brittle fracture , Nuclear reactors , Yield strength AND Tensile strength ,
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      Uranium-Molybdenum Alloy for Use in a Prompt-Burst Reactor

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    https://yetl.yabesh.ir/yetl1/handle/yetl/106512
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    contributor authorF. Rienecker
    contributor authorW. H. Moran
    date accessioned2017-05-08T23:31:57Z
    date available2017-05-08T23:31:57Z
    date copyrightDecember, 1965
    date issued1965
    identifier issn0098-2202
    identifier otherJFEGA4-27267#865_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/106512
    description abstractA large prompt-burst nuclear reactor, “Super Kukla,” required a core of material that would withstand unusually high stress levels resulting from rapid thermal expansion and inertia loads. An experimental investigation was undertaken to determine the properties of cast uranium—10 wt percent molybdenum alloy under static and dynamic conditions of loading at various temperatures for application in this reactor. Techniques were developed to cast, inspect by radiographic and ultrasonic means, machine, and nickel plate the material. Castings are in the form of rings, 30 in. OD, 18 in. ID, and 2 in. thick. Sound material with carbon content of less than 250 ppm was found to have a static yield strength of approximately 130,000 psi, ultimate strength of 133,000 psi, and elongation of 10 percent at room temperature. Sustained static loads of more than 40,000 psi in a normal atmosphere were found to induce a brittle fracture attributed to stress corrosion. Test specimens subjected to strain rates on the order of 20 in/in/sec withstood stresses of 200,000 psi in the gage region, but usually failed in the threaded ends.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleUranium-Molybdenum Alloy for Use in a Prompt-Burst Reactor
    typeJournal Paper
    journal volume87
    journal issue4
    journal titleJournal of Fluids Engineering
    identifier doi10.1115/1.3650831
    journal fristpage865
    journal lastpage870
    identifier eissn1528-901X
    keywordsAlloys
    keywordsmolybdenum
    keywordsUranium
    keywordsStress
    keywordsTemperature
    keywordsNickel
    keywordsMachinery
    keywordsInertia (Mechanics)
    keywordsThermal expansion
    keywordsGages
    keywordsSound
    keywordsMolybdenum alloys
    keywordsStress corrosion cracking
    keywordsCarbon
    keywordsElongation
    keywordsBrittle fracture
    keywordsNuclear reactors
    keywordsYield strength AND Tensile strength
    treeJournal of Fluids Engineering:;1965:;volume( 087 ):;issue: 004
    contenttypeFulltext
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