TARGETRY COUPLED SEPARATIONS
    1.
    发明申请

    公开(公告)号:US20220310281A1

    公开(公告)日:2022-09-29

    申请号:US17533264

    申请日:2021-11-23

    Abstract: Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

    Targetry coupled separations
    2.
    发明授权

    公开(公告)号:US10141079B2

    公开(公告)日:2018-11-27

    申请号:US14757683

    申请日:2015-12-23

    Abstract: Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

    Automated cleaning equipment and method for the nuclear fuel-cladding tube
    3.
    发明授权
    Automated cleaning equipment and method for the nuclear fuel-cladding tube 有权
    核燃料包壳管自动清洗设备及方法

    公开(公告)号:US08537960B2

    公开(公告)日:2013-09-17

    申请号:US12644877

    申请日:2009-12-22

    Abstract: Disclosed is an apparatus for performing an automated cleaning of nuclear fuel cladding-tubes. The apparatus comprises a pre-cleaning holding section disposed at a first side of the apparatus, a primary cleaning-material supplying section and a primary cleaning section disposed at a second side of the apparatus, a secondary cleaning section and a secondary cleaning material supplying section disposed at the second side of the apparatus and beside the primary cleaning section, an inspection section disposed at a third side of the apparatus that is opposite to the second side, and a post-cleaning holding section disposed at the fourth side of the transferring section. The pre-cleaning holding section and the post-cleaning holding section includes a cladding-tube guide where the cladding-tube is loaded before and after cleaning. Primary and secondary cleaning material supply sections are disposed at a lateral side of the primary and secondary cleaning sections respectively.

    Abstract translation: 公开了一种用于执行核燃料包层管的自动清洁的装置。 该设备包括设置在设备的第一侧的预清洁保持部分,设置在设备的第二侧的主要清洁材料供应部分和主要清洁部分,辅助清洁部分和辅助清洁材料供应部分 设置在设备的第二侧并且在主清洁部分旁边,设置在与第二侧相对的设备的第三侧的检查部分和设置在传送部分的第四侧的后清洗保持部分 。 预清洁保持部和后清洗保持部包括在清洁之前和之后装载包覆管的包覆管引导件。 主要和次要清洁材料供应部分分别设置在主要和次要清洁部分的侧面。

    Nuclear plant
    4.
    发明授权
    Nuclear plant 有权
    核电厂

    公开(公告)号:US08379789B2

    公开(公告)日:2013-02-19

    申请号:US13191627

    申请日:2011-07-27

    CPC classification number: G21C3/3206 G21C19/307 Y02E30/40

    Abstract: This invention relates to a nuclear plant having a reactor vessel and a fluid circuit including flow path defining means, defining a flow path for circulating a reactor coolant fluid from and to the reactor vessel. The nuclear plant includes a particle collection zone defined along at least part of the length of the flow path, and particle deflection means arranged in particle deflecting relationship with the flow path to deflect particles from a fluid stream in the flow path into or toward the particle collection zone.

    Abstract translation: 本发明涉及具有反应器容器和包括流路限定装置的流体回路的核电厂,其限定用于使反应堆冷却剂流体从反应器容器循环到反应器容器的流动路径。 核电厂包括沿着流路长度的至少一部分限定的颗粒收集区,以及颗粒偏转装置,其设置成与流动路径成颗粒偏转关系,以将颗粒从流动路径中的流体流中偏转到或朝向颗粒 收集区。

    Steam generator dual head sludge lance and process lancing system
    5.
    发明授权
    Steam generator dual head sludge lance and process lancing system 有权
    蒸汽发生器双头污泥喷枪和过程采血系统

    公开(公告)号:US08238510B2

    公开(公告)日:2012-08-07

    申请号:US12145828

    申请日:2008-06-25

    Inventor: Eric R. Haberman

    CPC classification number: F22B37/486 F28G1/166 F28G15/04

    Abstract: A method of cleaning sludge from the tube sheet (34) of a nuclear steam generator (10) includes introducing a moveable sludge lance (76) said moveable sludge lance having duel lance heads (77) through handholes (62) in the side of the generator and into a central tube lane (60) having a central stay rod (61) and sludge lancing with high pressure fluid through the row 1 tubes (85) in the tube lane, where the distance (200) between the dual lance heads (77) is wide enough to allow the dual lance heads to extend beyond the central stay rod (61).

    Abstract translation: 一种从核蒸汽发生器(10)的管板(34)清洗污泥的方法包括:将可移动污泥喷枪(76)引导到具有通过喷枪头(77)移动的污泥喷枪(76) 发生器并进入具有中心拉杆(61)的中心管道(60)和通过管道中的第1排管(85)的高压流体的污泥穿刺,其中双枪头( 77)足够宽以允许双喷枪头延伸超过中心拉杆(61)。

    Method of Decontaminating Radioisotope-Contaminated Surface Vicinity Region by Use of Nonthermal Laser Peeling Without Re-Melting, Without Re-Diffusion and Without Re-Contamination, and Apparatus Therefor
    6.
    发明申请
    Method of Decontaminating Radioisotope-Contaminated Surface Vicinity Region by Use of Nonthermal Laser Peeling Without Re-Melting, Without Re-Diffusion and Without Re-Contamination, and Apparatus Therefor 有权
    通过使用非再热熔融而不再次扩散和不再次污染的非热激光剥离对放射性同位素污染的表面附近区域进行去污染的方法及其装置

    公开(公告)号:US20100217060A1

    公开(公告)日:2010-08-26

    申请号:US12086387

    申请日:2007-03-29

    Inventor: Eisuke Minehara

    CPC classification number: G21F9/28 B23K26/0624 B23K26/142 Y10S588/90

    Abstract: The current methods of removing the surface-deposited layer contaminated by radioisotopes has the disadvantage of rigorous applicability conditions in such terms as the substance to be treated, the area and the shape, so the scope of their applicability is quite limited; in addition, 100% decontamination is not guaranteed and in spite of more than 50% that can be decontaminated, a greater part of the deposited radioisotopes remain unremoved, limiting the decontamination performance of the methods.Parts, structural components, etc. that have their surfaces contaminated by radioisotopes in the accelerators, nuclear reactors, RI product manufacturing factories, nuclear fuel factories, nuclear fuel reprocessing factories, etc. are decontaminated by non-thermal laser peeling without suffering re-melting, re-diffusing and re-contaminating such that upon non-thermal laser irradiation, areas near the irradiated surface are evaporated and removed faster than the heat generated in the irradiated surface is transmitted to nearby areas.

    Abstract translation: 目前除去放射性同位素污染的表面沉积层的方法具有严格的应用条件,如被处理物质,面积和形状等,其适用范围相当有限; 此外,100%的去污不能得到保证,尽管可以净化50%以上,但大部分沉积的放射性同位素仍然未被除去,限制了该方法的去污性能。 在加速器,核反应堆,RI产品制造工厂,核燃料工厂,核燃料后处理厂等表面被放射性同位素污染的部件,结构部件等,通过非热激光剥离进行去污染,不会再次熔化 ,再扩散和再污染,使得在非热激光照射下,照射表面附近的区域被蒸发并且被去除得快于被照射表面产生的热量被传送到附近的区域。

    Covering element for a reactor core of a nuclear installation, and nuclear reactor
    7.
    发明授权
    Covering element for a reactor core of a nuclear installation, and nuclear reactor 失效
    核装置反应堆核心的覆盖元件和核反应堆

    公开(公告)号:US07751522B2

    公开(公告)日:2010-07-06

    申请号:US11500035

    申请日:2006-08-07

    Abstract: A covering element for a reactor core of a nuclear installation provides a secure and tight closure of the reactor core in an operating state and at the same time being simple and cost effective to produce. The covering element is easily disassemblable during maintenance or loading processes and provides good possibilities for intervention in the reactor core. For this purpose, the covering element has a closure head and a separate support ring. The support ring is joined form-lockingly and/or force-lockingly to the closure head.

    Abstract translation: 用于核设备的堆芯的覆盖元件在操作状态下提供了反应堆堆芯的安全和紧密的封闭,并且同时制造简单且成本有效。 覆盖元件在维护或加载过程中易于拆卸,并为干燥堆芯提供了良好的可能性。 为此,覆盖元件具有闭合头和单独的支撑环。 支撑环以闭锁方式和/或强制锁定地接合到闭合头。

    Method of decontaminating a PWR primary loop
    9.
    发明授权
    Method of decontaminating a PWR primary loop 失效
    对PWR主回路进行净化的方法

    公开(公告)号:US5517539A

    公开(公告)日:1996-05-14

    申请号:US356820

    申请日:1994-12-15

    CPC classification number: G21C19/30 G21Y2002/303 G21Y2004/40

    Abstract: In a method of decontaminating a primary loop of a pressurized water reactor, including a steam generator, reactor coolant pump and hot and cold legs in the loop, the primary loop is isolated from a nuclear reactor vessel by closing hot leg and cold leg loop stop valves. Decontamination process water is circulated from one side of the steam generator channel head to the other side of the channel head via a bypass pipe extending between the cold leg and the hot leg without bypassing the water through steam generator tubes extending between the sides of the channel head. The level of the decontamination water in the steam generator is maintained at two to three feet in the tubes.

    Abstract translation: 在对包括蒸汽发生器,反应堆冷却剂泵以及回路中的冷热腿的压水反应堆的主回路进行净化的方法中,通过闭合热腿和冷腿循环停止将主回路与核反应堆隔离 阀门 净化处理水通过在冷腿和热腿之间延伸的旁通管而从蒸汽发生器通道头的一侧循环到通道头的另一侧,而不会通过在通道的两侧之间延伸的蒸汽发生器管绕过水 头。 蒸汽发生器中去污水的水平保持在管中2-3英尺处。

    Device for trapping migrating bodies within the secondary circuit of a
steam generator
    10.
    发明授权
    Device for trapping migrating bodies within the secondary circuit of a steam generator 失效
    用于捕集蒸汽发生器二次回路内迁移体的装置

    公开(公告)号:US5390219A

    公开(公告)日:1995-02-14

    申请号:US984682

    申请日:1992-12-02

    CPC classification number: F22B1/025

    Abstract: A device for trapping migrating bodies within the steam generator or secondary circuit of a nuclear installation is constituted by grids (6) placed between the upper part of the tube casing (8) and the pressure casing (7) of the steam generator. The meshes of the grids are so dimensioned as to prevent the passage of objects liable to jam between the tubes of the tube bundle of the primary circuit.

    Abstract translation: 用于捕集核装置的蒸汽发生器或二次回路内的迁移体的装置由设置在管壳(8)的上部与蒸汽发生器的压力壳(7)之间的格栅(6)构成。 栅格的网格的尺寸被设计成防止在主回路的管束的管之间容易堵塞的物体的通过。

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