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32 条记录 (耗时 0.011 秒)

    Systems and methods for fast molten salt reactor fuel-salt preparation
    2.
    发明授权
    Systems and methods for fast molten salt reactor fuel-salt preparation 有权

    公开(公告)号：US11062813B2

    公开(公告)日：2021-07-13

    申请号：US16900426

    申请日：2020-06-12

    申请人： Metatomic, Inc.

    发明人： Donald Ken Baer

    IPC分类号： G21C21/16 ,  G21C3/04 ,  G21C17/06 ,  G21C21/02 ,  G21F9/30 ,  G21C3/54

    摘要： The present disclosure provides systems and methods for fast molten salt reactor fuel-salt preparation. In one implementation, the method may comprise providing fuel assemblies having fuel pellets, removing the fuel pellets and spent fuel constituents from the fuel assemblies, granulating the removed fuel pellets or process feed to a chlorination process, processing the granular spent fuel salt into chloride salt by ultimate reduction and chlorination of the uranium and associated fuel constituents chloride salt solution, enriching the granular spent fuel salt, chlorinating the enriched granular spent fuel salt to yield molten chloride salt fuel, analyzing, adjusting, and certifying the molten chloride salt fuel for end use in a molten salt reactor, pumping the molten chloride salt fuel and cooling the molten chloride salt fuel, and milling the solidified molten chloride salt fuel to predetermined specifications.

    Ceramic nuclear fuel dispersed in a metallic alloy matrix
    6.
    发明授权
    Ceramic nuclear fuel dispersed in a metallic alloy matrix 有权

    公开(公告)号：US10424415B2

    公开(公告)日：2019-09-24

    申请号：US14680732

    申请日：2015-04-07

    申请人： ADVANCED REACTOR CONCEPTS LLC

    发明人： Leon C. Walters

    IPC分类号： G21C3/64 ,  G21C21/16 ,  G21C19/42

    摘要： Systems and methods for manufacturing metal fuel are described. Methods for fabricating a metal-fuel-matrix cermet nuclear fuel may include crushed ceramic particles combined with metallic fast reactor fuel via bottom pour casting or injection casting, or a powdered metallurgical process. A maximum quantity of crushed ceramic particles added to the metallic fuel must not exceed that which would fail to yield a continuous matrix of metal fuel. After a short irradiation period, the microstructure of the fuel may be substantially identical to that of injection cast fuel, without crushed ceramic particles, irrespective of the fabrication process. Thus, the extensive existing database for injection cast fuel, without crushed ceramic particles, may be an excellent indicator of expected irradiation performance. Each of the processes may contribute to a solution of the spent nuclear fuel problem and may denature Pu239 during the process.

    Method of improving wear and corrosion resistance of rod control cluster assemblies
    8.
    发明授权
    Method of improving wear and corrosion resistance of rod control cluster assemblies 有权
    提高杆控组合组件耐磨性和耐腐蚀性的方法

    公开(公告)号：US08699655B2

    公开(公告)日：2014-04-15

    申请号：US13044690

    申请日：2011-03-10

    申请人： Nagwa Mahmoud Elshaik

    发明人： Nagwa Mahmoud Elshaik

    IPC分类号： G21C21/16 ,  G21C7/10 ,  C23C16/34 ,  C23C16/50 ,  G21C21/00 ,  G21C7/00 ,  C23C16/00

    CPC分类号： C23C8/36 ,  C23C8/80 ,  G21C7/117 ,  G21C21/18 ,  Y02E30/39

    摘要： The present invention relates to tubular elements, such as fuel assembly tubes, which are designed to be used in high pressure and high temperature water in nuclear reactors, such as pressurized water nuclear reactors. In particular, the present invention relates to a method of improving wear resistance and corrosion resistance by depositing a protective coating having a depth of from about 5 to about 25 μm on the surface of the tubular elements. The coating is provided by nitriding the tubular element at a temperature of from about 400° C. to about 440° C. The nitridation of the tubular element can be carried out for a duration of from about 12 hours to about 40 hours.

    摘要翻译： 本发明涉及诸如燃料组装管的管状元件，其被设计用于核反应堆如压水核反应堆中的高压和高温水中。 特别地，本发明涉及通过在管状元件的表面上沉积具有约5至约25μm深度的保护涂层来改善耐磨性和耐腐蚀性的方法。 涂层通过在约400℃至约440℃的温度下氮化管状元件来提供。管状元件的氮化可以进行约12小时至约40小时的持续时间。