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1. 发明授权

US11289210B2 Method of making a nuclear reactor fuel duct 有权
公开(公告)号：US11289210B2
公开(公告)日：2022-03-29
申请号：US16167381
申请日：2018-10-22
申请人： TerraPower, LLC
发明人： Robert C. Petroski , Gary Povirk , Philip Schloss , Ashok Odedra , Michael E. Cohen
IPC分类号： G21C3/334 , G21C3/16 , G21C3/32 , G21C3/06 , G21C21/10 , G21C3/324 , G21C3/04
摘要： Disclosed embodiments include fuel ducts, fuel assemblies, methods of making fuel ducts, methods of making a fuel assembly, and methods of using a fuel assembly. An inner hollow structure has a first geometry and an outer hollow structure has a second geometry different from the first geometry. The first hollow structure is configured to expand in at least one dimension under stress and cause the first hollow structure to contact the second hollow structure. The second hollow structure distributes at least a portion of the stress of the first hollow structure.

2. 发明授权

US11127507B2 Fuel rod sensor system with inductive coupling 有权
公开(公告)号：US11127507B2
公开(公告)日：2021-09-21
申请号：US16564150
申请日：2019-09-09
申请人： Westinghouse Electric Company LLC
发明人： Jeffrey L. Arndt , Jorge V. Carvajal , Shawn C. Stafford
IPC分类号： G21C17/112 , G21C17/10 , G21C17/06 , G21C3/16
摘要： A sensor system for a fuel rod including a fuel pellet stack, the sensor system including a wireless interrogator disposed outside the fuel rod and a passive sensor component disposed within the fuel rod. The passive sensor component includes a receiver structured to receive an interrogation signal and output an excitation signal in response to receiving the interrogation signal, a reference transmitter structured to output a reference signal to the reference receiver in response to the excitation signal, a sensing transmitter structured to output a sensing signal to the sensing receiver in response to the excitation signal, and a core at least partially disposed within the sensing transmitter and coupled to move in conjunction with expansion or contraction of the fuel pellet stack, to move based on changes in pressure within the fuel rod, or to change temperature based on temperature changes within the fuel rod.

3. 发明申请

US20200027598A1 Detection Apparatus Usable In A Nuclear Reactor, and Associated Method 审中-公开
公开(公告)号：US20200027598A1
公开(公告)日：2020-01-23
申请号：US16214445
申请日：2018-12-10
申请人： Westinghouse Electric Company LLC
发明人： Jorge V. Carvajal , Jeffrey L. Arndt , Shawn C. Stafford , Melissa M. Heagy , John R. Abel II , Emre Tatli
IPC分类号： G21C17/10 , G01N29/036 , G21C3/16 , G01L7/04
摘要： A detection apparatus includes a resonant electrical circuit supported within an interior of a nuclear fuel rod generates a response pulse in response to an excitation pulse and transmits the response pulse through a cladding of the fuel rod to another location within a reactor in which the fuel rod is housed and without any breach in the cladding. A characteristic of the response pulse is indicative of a condition of the fuel rod. The detection apparatus also includes a transmitter positioned outside the cladding, in the reactor, in the vicinity of the fuel rod and configured to generate the excitation pulse and transmit the excitation pulse through the cladding to the resonant electrical circuit. A receiver is supported within the reactor outside of the cladding and, in response to the response pulse, communicates a signal to an electronic processing apparatus outside of the reactor.

4. 发明授权

US6002735A Nuclear fuel pellet 失效
公开(公告)号：US6002735A
公开(公告)日：1999-12-14
申请号：US988201
申请日：1997-11-26
申请人： Leonard F. P. Van Swam
发明人： Leonard F. P. Van Swam
IPC分类号： G21C3/58 , G21C3/62 , G21C3/16 , G21C3/32
CPC分类号： G21C3/58 , G21C3/623 , Y02E30/38
摘要： A nuclear fuel pellet having concentric layers of nuclear fuel in which an outer layer has less fissionable nuclear fuel per unit volume and substantially the same amount of fertile material per unit volume as an inner core.

5. 发明授权

US5061436A Gas cooled nuclear fuel element 失效
标题翻译：燃气冷核燃料元件
公开(公告)号：US5061436A
公开(公告)日：1991-10-29
申请号：US457033
申请日：1989-12-22
申请人： John R. Coiner, Jr.
发明人： John R. Coiner, Jr.
IPC分类号： G21C3/16
CPC分类号： G21C3/16 , Y02E30/40
摘要： A gas cooled nuclear fuel element having a particle fuel retention device which acts as a passive restraint in the event of failure of hot frit. A particle fuel retention device is positioned either in the annular space within the inner frit, in the end cap through which coolant gas flows, or attached to the end cap and extending axially beyond the fuel element.
摘要翻译：一种具有颗粒燃料保持装置的气体冷却核燃料元件，其在热玻璃料失效的情况下用作被动约束。颗粒燃料保持装置定位在内玻璃料内的环形空间中，冷却剂气体流过的端盖中，或者连接到端盖并且轴向延伸超过燃料元件。

6. 发明授权

US5002723A Nuclear fuel element 失效
标题翻译：核燃料元素
公开(公告)号：US5002723A
公开(公告)日：1991-03-26
申请号：US333934
申请日：1989-04-06
申请人： Roy W. Zocher
发明人： Roy W. Zocher
IPC分类号： G21C3/16 , G21C21/12
CPC分类号： G21C3/16 , G21C21/12 , Y02E30/40 , Y10T29/49826
摘要： A nuclear fuel element and a method of manufacturing the element. The fuel element is comprised of a metal primary container and a fuel pellet which is located inside it and which is often fragmented. The primary container is subjected to elevated pressure and temperature to deform the container such that the container conforms to the fuel pellet, that is, such that the container is in substantial contact with the surface of the pellet. This conformance eliminates clearances which permit rubbing together of fuel pellet fragments and rubbing of fuel pellet fragments against the container, thus reducing the amount of dust inside the fuel container and the amount of dust which may escape in the event of container breach. Also, as a result of the inventive method, fuel pellet fragments tend to adhere to one another to form a coherent non-fragmented mass; this reduces the tendency of a fragment to pierce the container in the event of impact.
摘要翻译：一种核燃料元件及其制造方法。燃料元件由金属初级容器和位于其内部并经常分段的燃料芯组成。主容器受到升高的压力和温度以使容器变形，使得容器符合燃料颗粒，即容器与颗粒的表面基本接触。这种一致性消除了允许燃料颗粒碎片和燃料颗粒碎片摩擦在容器上的间隙，从而减少燃料容器内的粉尘量以及在容器破裂的情况下可能逸出的灰尘的量。此外，作为本发明方法的结果，燃料颗粒碎片倾向于彼此粘附以形成相干的非碎裂物质; 这样可以减少碎片在发生冲击时刺穿容器的趋势。

7. 依法登记的发明

USH722H Nuclear reactor fuel with radially varying enrichment 失效
标题翻译：核反应堆燃料具有径向变化的浓缩
公开(公告)号：USH722H
公开(公告)日：1990-01-02
申请号：US252292
申请日：1988-09-30
申请人： George A. Sofer , James L. Maryott
发明人： George A. Sofer , James L. Maryott
IPC分类号： G21C3/16 , G21C3/326
CPC分类号： G21C3/16 , G21C3/326 , Y02E30/38
摘要： The fuel pellets inside the fuel rods of a boiling water reactor are made with a lower enrichment concentration in the axial radial region and a higher concentration near the peripheral radial region to reduce thermal expansion effects upon sudden rises in temperature of the pellet when the reactor power is abruptly increased by a rapid step-wise withdrawal of a control rod. At least rods immediately adjacent the control rods contain pellets of this type, but additional rods may also be of this construction.

8. 发明授权

US4684504A Bow resistant structural member for fuel assemblies in non-control rod locations of a nuclear reactor core 失效
标题翻译：核反应堆核心的非控制杆位置的燃料组件的弓形结构构件
公开(公告)号：US4684504A
公开(公告)日：1987-08-04
申请号：US748855
申请日：1985-06-26
申请人： John F. Wilson , Robert K. Gjertsen , Harry M. Ferrari
发明人： John F. Wilson , Robert K. Gjertsen , Harry M. Ferrari
IPC分类号： G21C3/33 , G21C3/16 , G21C3/30 , G21C3/326 , G21C3/32
CPC分类号： G21C3/326 , G21C3/16 , G21Y2002/303 , G21Y2004/30 , Y02E30/38
摘要： A fuel assembly for use at non-control rod locations of a nuclear reactor core includes top and bottom nozzles and longitudinal structural members extending between and attached to the nozzles for forming an integral unitary structure. One or more of the structural members includes an elongated hollow cladding tube extending between the top and bottom nozzles and end plugs secured to opposite ends of the tube for hermetically sealing and attaching the tube to the top and bottom nozzles. The improvements in the structural member relate to features for reducing fuel assembly bow. Such features relate to a quantity of thermal or irradiation-induced creep resistant material and pretensioning means positioned within the tube. The creep resistant material is a ceramic material in stacked pellet form and coated with a burnable adsorber material. The pretensioning means applies a predetermined compressive load to the ceramic pellet stack and reacts the load so as to preload the tube in a state of pretension having a magnitude sufficient to substantially counteract an axial load typically transmitted through the unitary structure of the fuel assembly and thereby greatly reduce the compressive stress in the structural member tube. There are two embodiments of the pretensioning means. In one embodiment, it is an elongated bellows type device positioned within the tube between the ceramic pellet stack and one of the tube ends, with the interior of the bellows type device being pressurized to create a predetermined axial force therein which places the ceramic pellet stack in compression and the tube in the state of pretension. In the other embodiment, it is an arrangement of belleville springs positioned within the tube between the ceramic pellet stack and one of the tube ends and stacked both in series and in parallel.
摘要翻译：在核反应堆核心的非控制杆位置使用的燃料组件包括顶部和底部喷嘴以及在喷嘴之间延伸并连接到喷嘴上以形成整体单一结构的纵向结构构件。一个或多个结构构件包括在顶部和底部喷嘴之间延伸的细长的中空包层管，以及固定到管的相对端的端塞，用于将管密封并附接到顶部和底部喷嘴。结构构件的改进涉及用于减少燃料组件弓的特征。这些特征涉及一定量的热或照射诱导的抗蠕变材料和位于管内的预张紧装置。抗蠕变材料是层叠的颗粒形式的陶瓷材料，并涂覆有可燃的吸附材料。预张紧装置将预定的压缩载荷施加到陶瓷颗粒堆叠并且使负载反应，以便在预紧力的状态下对管进行预加载，其尺寸足以基本上抵消通常通过燃料组件的整体结构传递的轴向载荷，从而大大降低了结构件管中的压应力。预紧装置有两个实施例。在一个实施例中，它是一个细长的波纹管式装置，其位于陶瓷颗粒堆叠与管端之一内的管内，波纹管型装置的内部被加压以在其中产生预定的轴向力，将陶瓷颗粒堆叠在压缩和管中处于预紧状态。在另一个实施例中，它是布置在管内的贝氏体弹簧的布置在陶瓷颗粒堆叠和管端之一之间，并且彼此串联并联。

9. 发明授权

US4477411A Nuclear reactor fuel elements 失效
标题翻译：核反应堆燃料元素
公开(公告)号：US4477411A
公开(公告)日：1984-10-16
申请号：US267014
申请日：1981-05-26
申请人： Edward D. Hindle
发明人： Edward D. Hindle
IPC分类号： G21C3/328 , G21C3/00 , G21C3/16 , G21C3/02
CPC分类号： G21C3/16 , G21Y2002/206 , G21Y2002/303 , G21Y2004/30 , Y02E30/40
摘要： An array of rods is assembled to form a fuel element for a pressurized water reactor, the rods comprising zirconium alloy sheathed nuclear fuel pellets and containing helium.The helium gas pressure is selected for each rod so that it differs substantially from the helium gas pressure in its closest neighbors. In a preferred arrangement the rods are arranged in a square lattice and the helium gas pressure alternates between a relatively high value and a relatively low value so that each rod has as its closest neighbors up to four rods containing helium gas at the other pressure value.
摘要翻译：一组棒组装成形成用于压水反应堆的燃料元件，该棒包括锆合金护套的核燃料颗粒并含有氦。对于每个棒选择氦气压力，使得其在最近的邻近处基本上与氦气压力不同。在优选的布置中，杆布置成正方形格子，并且氦气压力在相对高的值和相对较低的值之间交替，使得每个杆具有最多的相邻的最多四个棒，所述棒包含处于另一压力值的氦气。

10. 发明授权

US4393510A Reactor for production of U-233 失效
标题翻译：用于生产U-233的反应堆
公开(公告)号：US4393510A
公开(公告)日：1983-07-12
申请号：US701806
申请日：1976-07-01
申请人： Linton W. Lang , Robert L. Stetson
发明人： Linton W. Lang , Robert L. Stetson
IPC分类号： G21C3/16 , G21C5/20 , G21C3/22
CPC分类号： G21C5/20 , G21C3/16 , Y02E30/40
摘要： The production of a novel nuclear fuel utilizing clean uranium 233 in combination with other nuclear materials is made possible by utilization of an equally novel reactor configuration and method of operation. Clean uranium 233 is produced from thorium in a light water reactor while utilizing discrete separation of the thorium being irradiated from the fissile fuel. This clean uranium 233 is then incorporated directly as fissile isotope enrichment into a new nuclear fuel which may be done without encountering the usual difficulties and hazards in the handling of uranium 233 or the expense and delays associated with gaseous diffusion enrichment. The thorium from this process may be directly reprocessed for reactor charging without radiation hazard also.
摘要翻译：通过利用同样新颖的反应器构造和操作方法，可以利用利用清洁铀233与其它核材料组合的新型核燃料的生产。清洁铀233在轻水反应堆中由钍生产，同时利用从易裂变燃料照射的钍的离散分离。然后，这种干净的铀233直接作为裂变同位素浓缩结合到新的核燃料中，可以在不遇到处理铀233或与气体扩散富集相关的费用和延误方面遇到的常见困难和危险的情况下进行。来自该过程的钍可以直接再加工用于反应器充电而没有辐射危害。

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