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公开(公告)号：US11935661B2
公开(公告)日：2024-03-19
申请号：US17399859
申请日：2021-08-11
CPC分类号： G21C21/02 , G21C3/64 , B22F3/15 , B22F2301/20 , B64G1/408 , C22C1/05 , F02K7/02 , G21C5/02 , G21C5/12
摘要： CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.
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公开(公告)号：US20230059151A1
公开(公告)日：2023-02-23
申请号：US17790086
申请日：2021-01-21
发明人： Lance SNEAD , David SPROUSTER , Jason TRELEWICZ
摘要： Composite structures are provided whose composite matrix is a fully-dense (greater than 95%) magnesium oxide-containing phase and whose entrained phase, by virtue of its' decomposition temperature or chemical reactivity, would otherwise not be fabricable. Notably, a methodology is provided whereby a range of composite structures are formed by applying an advanced manufacturing technique and a blend of ceramic powder whose sintering is enhanced by small amounts of a metal halide sintering aid. This methodology and process significantly lowers the processing temperature of refractory ceramics such as magnesium oxide allowing formation of ceramic bodies incorporating phases such as metal hydrides, fragile ceramic phases, and highly reactive species such as beryllides. In all cases, the final product is substantially-free, or even devoid, of the metal halide sintering aid, resulting in a phase-pure ceramic matrix composed of the host phase and the entrained phase.
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公开(公告)号：US11456083B2
公开(公告)日：2022-09-27
申请号：US16611328
申请日：2018-04-16
发明人： Simon Middleburgh , Mattias Puide
摘要： A nuclear fuel pellet for a nuclear reactor is disclosed. The pellet comprises a metallic matrix and ceramic fuel particles of a fissile material dispersed in the metallic matrix. The metallic matrix is an alloy consisting of the principle elements U, Zr, Nb and Ti, and of possible rest elements. The concentration of each of the principle elements in the metallic matrix is at the most 50 molar-%.
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公开(公告)号：US20220115152A1
公开(公告)日：2022-04-14
申请号：US17399881
申请日：2021-08-11
发明人： Eric A. BARRINGER , Russell R. JENSEN , Jeremy L. GUSTAFSON , Matt ALES , Joshua J. BERGMAN , Ryan T. SWANSON , Jonathan K. WITTER , Danny GALICKI , James B. INMAN , Matt KRECICKI , Roger RIDGEWAY
摘要： Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC—SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a NTP reactor.
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公开(公告)号：US20150294747A1
公开(公告)日：2015-10-15
申请号：US14680732
申请日：2015-04-07
发明人： Leon C. Walters
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.
摘要翻译： 描述了用于制造金属燃料的系统和方法。 用于制造金属 - 燃料 - 基质金属陶瓷核燃料的方法可以包括通过底部浇铸或注射铸造与金属快速反应堆燃料结合的粉碎陶瓷颗粒，或粉末冶金方法。 添加到金属燃料中的最大量的粉碎的陶瓷颗粒不得超过不能产生金属燃料的连续基质的颗粒。 在短的照射时间之后，不管制造过程如何，燃料的微结构可以与没有粉碎的陶瓷颗粒的注射铸造燃料的显微组织基本相同。 因此，广泛的现有的注射铸造燃料数据库，没有破碎的陶瓷颗粒，可能是预期辐射性能的一个很好的指标。 每个过程可能有助于解决乏燃料问题，并可能在该过程中使Pu239变性。
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公开(公告)号：US4267019A
公开(公告)日：1981-05-12
申请号：US904518
申请日：1978-05-10
摘要： Coated nuclear fuel particles are made by first pyrolytically depositing low density carbon onto fuel cores and thereafter depositing a fission-product retentive, higher density exterior coating. In the improvement, cores of uranium, thorium or plutonium oxides are coated by co-depositing silicon carbide or zirconium carbide along with the low density pyrocarbon to create a uniform dispersion. Silicon or zirconium is deposited in an amount equal to at least about one atom for each fission anticipated during the fuel lifetime.
摘要翻译： 涂覆的核燃料颗粒通过首先将低密度碳热解沉积到燃料芯上，然后沉积裂变产物保持性，更高密度的外部涂层来制备。 在改进中，通过与低密度热解碳一起共沉积碳化硅或碳化锆来涂覆铀，钍或钚氧化物的核心以产生均匀的分散体。 对于在燃料寿命期间预期的每个裂变，硅或锆以等于至少约一个原子的量沉积。
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公开(公告)号：US4189398A
公开(公告)日：1980-02-19
申请号：US448546
申请日：1965-04-15
CPC分类号： G21C3/64 , Y02E30/38 , Y10S376/901
摘要： 1. A high temperature graphite-uranium base nuclear fuel composition containing from about 1 to about 5 five weight percent rhenium metal.
摘要翻译： 1.含有约1至约5重量％铼金属的高温石墨 - 铀基燃料组合物。
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8.发明授权Process for the production of fuel combined articles for addition in block shaped high temperature fuel elements 失效用于生产用于在块状高温燃料元件中添加的燃料组合制品的方法
公开(公告)号：US3975471A
公开(公告)日：1976-08-17
申请号：US489436
申请日：1974-07-17
申请人： Milan Hrovat , Lothar Rachor
发明人： Milan Hrovat , Lothar Rachor
摘要： There is provided a process for the production of fuel compacts consisting of an isotropic, radiation resistant graphite matrix of good heat conductivity having embedded therein coated fuel and/or fertile particles for insertion into high temperature fuel elements by providing the coated fuel and/or fertile particles with an overcoat of molding mixture consisting of graphite powder and a thermoplastic resin binder. The particles after the overcoating are provided with hardener and lubricant only on the surface and subsequently are compressed in a die heated to a constant temperature of about 150.degree.C., hardened and discharged therefrom as finished compacts.
摘要翻译： 提供了一种用于生产由具有良好导热性的各向同性，耐辐射的石墨基质组成的燃料压块的方法，该石墨基质嵌入其中涂覆的燃料和/或通过提供涂覆的燃料和/或可育的 具有由石墨粉末和热塑性树脂粘合剂组成的模制混合物外涂层的颗粒。 在外涂层之后的颗粒仅在表面上提供硬化剂和润滑剂，随后在加热到约150℃的恒温的模具中被压缩，硬化并作为成品压块从其中排出。
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公开(公告)号：US3865614A
公开(公告)日：1975-02-11
申请号：US80381059
申请日：1959-04-02
发明人： NEWBURY RAY S , TULLY JR GEOFFREY R
CPC分类号： C04B41/009 , C04B35/52 , C04B41/52 , C04B41/89 , C04B2111/00862 , G21C3/28 , G21C3/64 , Y02E30/38 , C04B41/4535 , C04B41/4556 , C04B41/457 , C04B41/5057 , C04B41/463
摘要： 1. In a process for producing a tenacious zirconium carbide coating on graphite impregnated with uranium comprising the steps of impregnating a piece of porous graphite with uranyl nitrate dihydrate dissolved in tertiary butyl alcohol, enveloping said graphite piece in clean tertiary butyl alcohol solvent to dissolve said uranyl nitrate dihydrate impregnant from the surface of said graphite into a liquid, enveloping said graphite piece in liquid nitrogen to freeze said impregnated solution, evaporating said frozen solvent therefrom, whereby said uranyl nitrate dihydrate is deposited within said graphite pores, converting said uranium to the carbide by the application of heat, outgassing said graphite, applying a coating of finely divided zirconium suspended in liquid containing a carbonaceous binder onto said graphite surface, evaporating said liquid and converting said zirconium to the carbide by the application of heat whereby a zirconium carbide coating is obtained.
摘要翻译： 1.在用铀浸渍的石墨上生产顽固的碳化锆涂层的方法，包括以下步骤：将一块多孔石墨与硝酸铀酰二水合物浸渍在叔丁醇中，将所述石墨片包封在干净的叔丁醇溶剂中以溶解所述 将硝酸铀酰二水合物浸渍剂从所述石墨的表面浸入液体中，将所述石墨片包封在液氮中以冷冻所述浸渍溶液，从其中蒸发所述冷冻溶剂，由此所述硝酸铀酰二水合物沉积在所述石墨孔内，将所述铀转化为 通过施加热量，除气所述石墨，将悬浮在含有碳质粘合剂的液体中的细碎锆涂层施加到所述石墨表面上，蒸发所述液体并通过施加热量将所述锆转化为碳化物，由此碳化锆涂层 获得。
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公开(公告)号：US3862908A
公开(公告)日：1975-01-28
申请号：US63566267
申请日：1967-05-03
申请人： GRACE W R & CO
发明人： FITCH FREDERICK T , BRAUN ANN B
CPC分类号： C04B35/01 , B01J2/08 , C04B35/51 , C04B35/626 , G21C3/623 , G21C3/64 , Y02E30/38 , Y10S376/901
摘要： As compositions of matter non-agglomerating microspheres of oxides in the 5 to 500 micron size range. The particles have a uniform crystallite structure with a grain size of 1 micron or less, and a sigma value derived from the equation Sigma D/Ds of about 1 to 1.3.
摘要翻译： 作为5至500微米尺寸范围内的氧化物的物质非附聚微球的组合物。 颗粒具有晶粒尺寸为1微米或更小的均匀微晶结构，并且由方程式Sigma = D / Ds得到约1至1.3的σ值。
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