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公开(公告)号：US20220301732A1
公开(公告)日：2022-09-22
申请号：US17640033
申请日：2020-10-04
摘要： An enhanced architecture for a nuclear reactor core includes several technologies: (1) nuclear fuel tiles (S-Block); and (2) a high-temperature thermal insulator and tube liners with a low-temperature solid-phase moderator (U-Mod) to improve safety, reliability, heat transfer, efficiency, and compactness. In S-Block, nuclear fuel tiles include a fuel shape designed with an interlocking geometry pattern to optimize heat transfer between nuclear fuel tiles and into a fuel coolant and bring the fuel coolant in direct contact with the nuclear fuel tiles. Nuclear fuel tiles can be shaped with discontinuous nuclear fuel lateral facets and have fuel coolant passages formed therein to provide direct contact between the fuel coolant and the nuclear fuel tiles. In U-Mod, tube liners with low hydrogen diffusivity retain hydrogen in the low-temperature solid-phase moderator even at elevated temperatures and the high-temperature thermal insulator insulates the solid-phase moderator from the nuclear fuel tiles.
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公开(公告)号：US11183311B2
公开(公告)日：2021-11-23
申请号：US15966552
申请日：2018-04-30
摘要： A fuel assembly for a pressure-tube nuclear reactor includes a fuel channel assembly. The fuel channel assembly has an outer conduit and an inner conduit received within the outer conduit. The conduits define an annular fuel bundle chamber for receiving a flow of a coolant in one direction. The inner conduit includes a central flow passage for receiving a flow of the coolant in an opposite direction. A fuel bundle positioned within the fuel bundle chamber consists of fuel elements arranged to form an inner ring surrounding the inner conduit, and an outer ring surrounding the inner ring. The coolant may be light water, and geometries of the fuel assembly may be selected so moderation by the volume of coolant promotes generally uniform power distribution in the fuel elements.
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公开(公告)号：US11079054B2
公开(公告)日：2021-08-03
申请号：US15735374
申请日：2016-06-22
IPC分类号： F16L39/00 , F16L9/19 , F28F9/26 , F28D7/10 , F28F13/06 , G21C3/322 , G21C15/02 , G21C3/328 , G21C1/20 , G21C21/00
摘要： A cross-over fluid coupling includes a first coupling end and a second coupling end. A plurality of first conduits have inner ends disposed toward the first coupling end and outer ends spaced apart from the inner end toward the second coupling end and being outboard of the inner end. A plurality of second conduits have outer ends that are disposed toward the first coupling end and positioned laterally outboard of the inner end of at least one of the first conduits, and inner ends that are spaced apart from the outer end toward the second coupling end in the axial direction and is laterally inboard of the outer end of the at least one of the first conduits.
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公开(公告)号：US20180144834A1
公开(公告)日：2018-05-24
申请号：US15577611
申请日：2016-05-27
摘要： The invention relates to the field of nuclear energy, more particularly to low-power and particularly low-power reactors. A nuclear reactor contains a housing with a reflector which forms a reactor core. The core has arranged therein primary process tubes, which are intended for circulating a coolant, and secondary process tubes, which are intended for accommodating elements of a control and protection system. The reactor also contains an intake chamber for coolant of a primary loop, and a discharge chamber for coolant of the primary loop, which are separated by a partition. The primary process tubes are designed in the form of Field tubes, the outer tubes of which are secured on the bottom of the intake chamber for the coolant of the primary loop, and the inner tubes are secured on the partition. Fuel assemblies are mounted in the inner tubes of the Field tubes on suspensions, which are secured on an upper portion of the discharge chamber for the coolant of the primary loop. The secondary process tubes are sealed off from the intake and discharge chambers for the coolant of the primary loop, and the inter-tube space of the core is filled with a medium or material which is transparent to neutrons.
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26.发明授权Nuclear reactor cores comprising a plurality of fuel elements, and fuel elements for use therein 有权包括多个燃料元件的核反应堆核心和用于其中的燃料元件公开(公告)号：US09418765B2
公开(公告)日：2016-08-16
申请号：US13829812
申请日：2013-03-14
申请人： Roger Ian Lounsbury
发明人： Roger Ian Lounsbury
摘要： In a nuclear reactor core, each of a plurality of pressure tubes contains fuel elements spaced apart to permit coolant to flow through spaces between adjacent fuel elements. Each fuel element comprises fuel pellets in cladding, e.g., sapphire, having a melting temperature of at least 1900° C. and does not form significant hydrogen if exposed to high temperature steam. Each pressure tube has an internal insulator sleeve, e.g., fused silica, that has relatively low thermal conductivity over a range of normal operating temperatures and relatively high thermal radiation transmission at temperatures higher than said normal operating temperature range. When coolant is absent from said spaces, the insulator sleeve transmits to the pressure tube at least about 10%, but preferably more than about 40% of thermal radiation from the fuel for conduction through the pressure tube to the moderator and fuel temperature remains within safe limits after the reactor is shut down.
摘要翻译： 在核反应堆芯中，多个压力管中的每一个包含间隔开的燃料元件，以允许冷却剂流过相邻燃料元件之间的空间。 每个燃料元件包括包层中的燃料颗粒，例如蓝宝石，其熔化温度至少为1900℃，如果暴露于高温蒸汽中，则其不形成显着的氢气。 每个压力管具有内部绝缘体套管，例如熔融二氧化硅，其在正常工作温度的范围内具有相对低的导热性，并且在高于所述正常工作温度范围的温度下具有相对较高的热辐射透射率。 当冷却剂从所述空间中不存在时，绝缘体套筒向压力管传递至燃料的至少约10％，但优选大于约40％的热辐射，以通过压力管传导至减速器，燃料温度保持在安全状态 反应堆关闭后的极限。
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27.发明授权Manufacturing method of delayed hydride cracking resistant seamless pressure tube made of zirconium (Zr) alloy 失效由锆（Zr）合金制成的延迟氢化物抗裂无缝压管的制造方法
公开(公告)号：US5681406A
公开(公告)日：1997-10-28
申请号：US249296
申请日：1994-05-25
申请人： Seong-Su Kim , Dae-Whan Kim , Joon-Wha Hong , Young-Whan Kang
发明人： Seong-Su Kim , Dae-Whan Kim , Joon-Wha Hong , Young-Whan Kang
摘要： A method for manufacturing a delayed hydride cracking resistant zirconium ahoy (Zircaloy-2, Zircaloy-4, Zr-2.5% Nb, pure Zr, etc.) pressure tube includes the steps of making a seamless pressure tube having a diameter smaller than the final size by extrusion or drawing, and then expanding the tube at a temperature below 600.degree. C. by cross rolling.
摘要翻译： 制造延迟氢化物抗裂锆锆（Zircaloy-2，Zircaloy-4，Zr-2.5％Nb，纯Zr等）压力管的方法包括以下步骤：制造直径小于最终的无缝压力管 通过挤出或拉伸，然后通过交叉轧制在低于600℃的温度下膨胀管。
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公开(公告)号：US4986112A
公开(公告)日：1991-01-22
申请号：US409781
申请日：1989-09-20
申请人： James R. Hopkins , Brian Strachan
发明人： James R. Hopkins , Brian Strachan
CPC分类号： G21C13/10 , Y02E30/40 , Y10S220/917
摘要： A pressure vessel for fluids containing hydrogen and subjected to a neutron flux. The vessel comprises an inner sealing layer and an outer load bearing layer. The inner sealing layer is composed of a material having a radiation induced diametral deformation rate higher than that of the outer layer to minimize stresses therein. The outer layer is provided with apertures, and the boundary between the inner and outer layers is non-metallurgical such that any fluid which penetrates the sealing layer will readily pass through the outer layer where it can be detected, by suitable detector before it produces embrittlement of the load bearing layer. The preferred application for the invention is in pressure tubes for a nuclear reactor.
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公开(公告)号：US4302287A
公开(公告)日：1981-11-24
申请号：US884571
申请日：1978-03-08
申请人： Hiroshi Hayashi
发明人： Hiroshi Hayashi
CPC分类号： G21C7/00 , G21C1/20 , G21Y2002/201 , G21Y2004/40 , Y02E30/39
摘要： A method for controlling the operation of a nuclear reactor to increase the reactor power in a range in which pellet-clad-mechanical-interaction occurs. The method includes the steps of increasing the reactor power from a power level in which pellet-clad-mechanical-interaction begins to take place up to a predetermined power level for the nuclear reactor and controlling the rate of increase of the linear heat generating rate. The rate of increase is controlled with at least one of a rate no less than 0.15 KW/ft/hr., and a rate no greater than a predetermined critical rate so as to shorten the time necessary to raise the reactor power to the predetermined power level without causing pellet-clad-mechanical-interaction damage to the fuel elements.
摘要翻译： 一种用于控制核反应堆的操作以在发生丸粒包层机械相互作用的范围内增加反应堆功率的方法。 该方法包括以下步骤：从堆芯 - 机械相互作用开始发生到核反应堆的预定功率水平并控制线性发热速率的增加速率的功率水平增加反应堆功率。 增加率以不低于0.15KW / ft / hr的速率和不大于预定临界速率的速率中的至少一种来控制，以便缩短将反应堆功率提高到预定功率所需的时间 而不会对燃料元件造成颗粒包层 - 机械相互作用损坏。
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公开(公告)号：US3963534A
公开(公告)日：1976-06-15
申请号：US446799
申请日：1974-02-28
CPC分类号： G21C3/07 , C22C16/00 , C22F1/186 , G21C1/20 , G21Y2002/103 , G21Y2004/101 , Y02E30/40 , Y10S376/90
摘要： In a method of fabrication of nuclear reactor components such as fuel cans and pressure tubes, use is made of zirconium alloys such as Zircaloy 2 or Zircaloy 4 having an oxygen content of 0.14 to 0.25 % by weight. The components are subjected to an annealing operation at a temperature within the range of 400.degree. to 750.degree.C and especially 525.degree. to 750.degree.C over a period of approximately two hours, thus resulting in recrystallization.
摘要翻译： 在制造核反应堆组件如燃料罐和压力管的方法中，使用氧含量为0.14至0.25重量％的锆合金，例如Zircaloy 2或Zircaloy 4。 在大约2小时的时间内，将组分在400〜750℃，特别是525〜750℃的温度下进行退火处理，得到重结晶。
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