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公开(公告)号：US20190318836A1
公开(公告)日：2019-10-17
申请号：US15952042
申请日：2018-04-12
申请人： Michael Greene
发明人： Michael Greene
摘要： A method and system for generating and maintaining a solid structure is provided. The system includes a frame composed of an interconnected network of pipes configured for transporting liquid, the frame having a substantially spherical shape, a plurality of nozzles uniformly distributed along the pipes, wherein the plurality of nozzles are configured for dispensing liquid, a repository that holds a liquid composed of water and at least one additive, a refrigeration unit configured for refrigerating the liquid from the repository to at least a freezing temperature, and a pump for pumping the liquid from the refrigeration unit through the pipes and out of the nozzles, wherein the system is configured to dispense the liquid at said freezing temperature so as to freeze upon egress and create a solid structure surrounding the pipes. The system may also return melted liquid from the solid structure to the repository.
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公开(公告)号：US10286494B2
公开(公告)日：2019-05-14
申请号：US15018961
申请日：2016-02-09
发明人： Akira Yamamoto , Yoshiaki Ono , Daiki Maruyama
IPC分类号： B23K31/02 , G21C13/00 , G21C13/02 , G21C13/08 , B23K101/12 , G21C13/024 , G21C13/087 , G21C13/093
摘要： A method for manufacturing a core barrel according to the embodiment includes: welding one end part of a short ring to a lower core support plate; and machining the lower core support plate to which the short ring is welded. The machining of the lower core support plate includes forming a placement surface on which the fuel assembly is to be placed; and forming a fuel alignment pin hole, in which a fuel alignment pin for positioning the fuel assembly is to be inserted. After the machining of the lower core support plate, a main body barrel is welded to the other end part of the short ring, where the main body barrel covers the reactor core including the fuel assembly to be placed on the placement surface.
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53.发明授权公开(公告)号：US09947425B2
公开(公告)日：2018-04-17
申请号：US14909903
申请日：2014-08-08
申请人： AREVA GmbH
CPC分类号： G21F9/30 , G21C13/08 , G21C17/0225 , G21C19/28 , G21C21/00 , G21F9/004 , G21F9/28 , Y02E30/40
摘要： The invention relates to a method for reducing the radioactive contamination of the surface of a component used in a nuclear reactor, which component is in contact with radioactively contaminated water, in which method a hydrophobic film is produced on the surface of a component by virtue of the surface being wetted with an aqueous solution which contains a film-forming amphiphilic substance.
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公开(公告)号：US5442667A
公开(公告)日：1995-08-15
申请号：US212979
申请日：1994-03-15
申请人： Gregor Senski
发明人： Gregor Senski
IPC分类号： G21C9/00 , G21C13/00 , G21C13/087 , G21C13/08
CPC分类号： G21C13/087 , Y02E30/40
摘要： A reactor pressure vessel for a nuclear reactor includes an upper part and a lower part. At least the lower part has first subregions with a lesser wall thickness and second subregions with a greater wall thickness. The lesser wall thickness is selected for a rated operation. The first subregions are formed by recesses in the outer surface of the wall.
摘要翻译： 用于核反应堆的反应堆压力容器包括上部和下部。 至少下部具有较小壁厚的第一子区域和具有较大壁厚的第二子区域。 选择较小的壁厚进行额定运行。 第一子区域由壁的外表面中的凹部形成。
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公开(公告)号：US4892702A
公开(公告)日：1990-01-09
申请号：US258358
申请日：1988-10-17
申请人： Alain Vignes
发明人： Alain Vignes
CPC分类号： G21C13/087 , B23K15/0093 , B23K15/04 , Y02E30/40
摘要： A vessel comprising a shell of large thickness, for example between 200 and 300 mm, consists of unit components symmetrical in revolution (2a, 2b, 6, 7, 8, 9, 10, 3a, 3b) and connected together by end-to-end welding. The components are made of a steel containing 2 to 2.50% of chromium, 0.9 to 1.1% of molybdenum and less than 0.15% of carbon. The welding for connecting these unit components is performed by means of an electron beam in a single pass over the entire thickness of the components, without filler metal. the invention applies particularly to the manufacture of a vessel for a pressurized-water nuclear reactor.
摘要翻译： 包括厚度大的壳体（例如200至300mm）的容器由旋转对称的单元部件（2a，2b，6,7,8,9,10a，3b，3b）组成，并通过端部连接到 - 焊接。 这些部件由含有2至2.50％的铬，0.9至1.1％的钼和小于0.15％的碳的钢制成。 用于连接这些单元部件的焊接通过电子束在组件的整个厚度上单次通过，而不需要填充金属。 本发明特别适用于制造用于加压 - 水核反应堆的容器。
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公开(公告)号：US4801421A
公开(公告)日：1989-01-31
申请号：US26501
申请日：1987-03-16
IPC分类号： G21C17/003 , G21C13/08 , G21C17/00 , G21C17/108
CPC分类号： G21C13/08 , G21C17/00 , G21C17/108 , Y02E30/40
摘要： A real time analysis of nuclear reactor vessel integrity is preformed by monitoring reactor coolant temperature and pressure and fast neutron fluence, and generating therefrom a visual comparison of the reference nil-ductility transition temperature, RT.sub.ndt, required for flaw initiation and the actual RT.sub.ndt through the entire depth of the vessel wall at selected critical locations. When flaw initiation is indicated at any depth, the RT.sub.ndt required for flaw propagation arrest is also generated and displayed. A display can also be generated to provide guidance for optimum performance during heatup and cooldown. Thermocouples located at the reactor core inlet are used in conjunction with the resistance temperature detectors, RTDs, conventionally provided in the cold leg conduits to generate a more accurate measurement of the coolant temperature at the critical locations in the vessel. Under stagnant flow conditions a correlation is applied to the RTD readings to provide the best estimate of coolant temperature at the critical locations.
摘要翻译： 核反应堆容器完整性的实时分析是通过监测反应堆冷却剂温度和压力以及快中子通量来实现的，并通过对其产生缺陷引发所需的参考无延展转变温度RTndt和通过实际RTndt进行视觉比较 在选定的关键位置的血管壁的整个深度。 当在任何深度指示缺陷开始时，也产生并显示缺陷传播停止所需的RTndt。 还可以生成显示器，以提供在加热和冷却期间的最佳性能的指导。 位于反应堆核心入口处的热电偶与冷腿管道中通常设置的电阻温度检测器RTD结合使用，以在容器中的关键位置产生更准确的冷却剂温度测量。 在停滞的流动条件下，将相关性应用于RTD读数，以提供关键位置的冷却剂温度的最佳估计。
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公开(公告)号：US4111327A
公开(公告)日：1978-09-05
申请号：US652853
申请日：1976-01-27
申请人： Nikolai Janakiev
发明人： Nikolai Janakiev
CPC分类号： F16J12/00 , B01J3/04 , G21C13/08 , Y02E30/40 , Y10T292/218 , Y10T292/221
摘要： The cylindrical body of a pressure vessel for use as a reaction vessel, is built up from courses of flat circularly arcuate segmental plates, the courses being located with respect to each other by locating means passing through aligning openings in the plates. To facilitate construction the openings in each plate are disposed in a symmetrical pattern or array. The locating means may be pins or preferably sleeves, and prestressing means for holding the courses together may be provided by tie-rods or cables passing through such sleeves and also possibly through openings not taken up by locating means. The floor and/or cover of the pressure vessel may be double-walled, and prestressing means provided within the double walls for tightly securing the floor and/or cover to the inside of the cylindrical wall.
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公开(公告)号：US4040876A
公开(公告)日：1977-08-09
申请号：US485465
申请日：1974-07-02
CPC分类号： G21C3/07 , C22C38/44 , Y02E30/40 , Y10S376/90
摘要： An alloy consisting essentially of from about 14% to 19% chromium, from 25 to 35% of nickel, from about 2% to 3% molybdenum, from about 0.1% to 1% of silicon, up to 0.5% of manganese, from about 0.03 to 0.05% carbon, up to about 0.01% sulfur, up to about 0.01% of phosphorus, up to 0.01% boron, up to about 0.01% oxygen, up to about 0.02% nitrogen, small amounts of incidental impurities, and the balance being iron, the alloy having an N.sub.v (average electron vacancy number) value of between 1.6 and 2.8, has an unexpected combination of properties enabling it to be formed by hot and cold working and heat treatment into components and members particularly suitable for use in nuclear reactors wherein the components are subjected to molten sodium, where the corrosion of the surface of the alloy is not in excess of the order of 1 to 2 mils per year, and the alloy exhibits low swelling when exposed to intense radiation, while exhibiting good physical properties at temperatures of up to 1325.degree. F. Worked and heat treated alloy members are usable as fuel cladding, grid supports, ducts and other sodium contacting in-core components that may be spaced in close predetermined relationship to ensure high reactor performance, particularly in breeder reactors, for the desired useful life thereof.
摘要翻译： 基本上由约14％至19％的铬，25至35％的镍，约2％至3％的钼，约0.1％至1％的硅，至多0.5％的锰，从约 0.03至0.05％的碳，至多约0.01％的硫，至多约0.01％的磷，至多0.01％的硼，至多约0.01％的氧，至多约0.02％的氮，少量附带的杂质，以及余量 作为铁，具有1.6至2.8之间的Nv（平均电子空位数）值的合金具有预期的特性组合，使得其能够通过热和冷加工形成，并且热处理成特别适合用于核的部件和部件 其中组分经受熔融钠的反应器，其中合金表面的腐蚀不超过每年1至2密耳的数量级，并且当暴露于强烈辐射时，合金表现出低膨胀，同时呈现良好的物理 特性温度高达1325°F 工作和热处理的合金构件可用作燃料包层，网格支撑件，管道和其它可接近预定关系的钠接触核心部件，以确保高的反应器性能，特别是在增殖反应器中的期望使用寿命 。
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59.发明授权Nuclear reactor pressure vessel for nuclear reactors with plastically deformable spacers 失效具有塑性变形间隙的核反应堆的核反应堆压力容器
公开(公告)号：US4011132A
公开(公告)日：1977-03-08
申请号：US543136
申请日：1975-01-22
申请人： Hermann Kumpf , Gottfried Molz
发明人： Hermann Kumpf , Gottfried Molz
摘要： Cylindrical pressure vessel structure for nuclear reactors comprises a steel pressure vessel adapted to receive therein a pressurizing medium, a concrete enclosure at least partly producible in situ, the steel pressure vessel being mounted within the concrete enclosure and, in unheated and unpressurized condition, being radially and axially spaced from the concrete enclosure, and a supporting and insulating layer secured in the radially extending space between the steel pressure vessel and the concrete enclosure, the steel pressure vessel, during operating condition thereof wherein the steel pressure vessel is heated and pressurized, being expansible so as to bear through the supporting and insulating layer against the concrete enclosure, the supporting and insulating layer having support plates on the side thereof adjacent the steel pressure vessel, spacer members connected with the support plates and projecting beyond the surface of the support plates in direction toward the steel pressure vessel, the spacer members being yieldable to a predetermined force for a given radial distance corresponding substantially to an intermediate space between the supporting and insulating layer and the steel pressure vessel.
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公开(公告)号：US3794559A
公开(公告)日：1974-02-26
申请号：US3794559D
申请日：1971-07-27
IPC分类号： G21C11/08 , G21C13/093 , G21C15/12 , G21C13/08
CPC分类号： G21C13/0933 , G21C11/08 , G21C15/12 , Y02E30/34
摘要： A concrete pressure vessel having a lined cavity for hot, chemically aggressive liquid disposed within a cooling jacket with a layer of material of high thermal conductivity between the cavity liner and the cooling jacket, the jacket and high thermally conductive layer serving to maintain the temperature of the cavity liner within closely controlled limits and the maximum temperature of the main body of the vessel at an acceptable level, and the jacket and the conductive layer also serving to prevent leakage of liquid from the cavity.
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