WELDING DEVICE AND METHOD OF MANUFACTURE

    公开(公告)号:US20230125948A1

    公开(公告)日:2023-04-27

    申请号:US17970838

    申请日:2022-10-21

    申请人: BWXT Canada Ltd.

    IPC分类号: B23K9/16 B23K9/28

    摘要: A welding device, having a body configured to route power, a first inlet and a first outlet formed on the body, the first inlet configured to receive a shielding gas, a first channel extending through the body and connecting the first inlet and the first outlet, a second inlet and a second outlet formed on the body, the second inlet configured to receive a coolant, a second channel extending through the body and connecting the second inlet with the second outlet, the second channel having a convoluted portion comprising a plurality of segments configured to increase a proportion of the second channel relative to the body.

    Tube support system for nuclear steam generators

    公开(公告)号:US11448393B2

    公开(公告)日:2022-09-20

    申请号:US15250513

    申请日:2016-08-29

    申请人: BWXT Canada Ltd.

    摘要: Apparatus for a steam generator that employs tube support plates within a shroud that is in turn disposed within a shell. The tube support plates are made of a material having a coefficient of thermal expansion lower than that of the shroud. The tube support plates are aligned during fabrication, with minimal clearances between components. Using a tube support displacement system, a controlled misalignment is then imposed on one or more tube support plates, as the steam generator heats up. The tube support plate displacement system has only one part, a push rod, which is internal to the steam generator shroud, thereby minimizing the potential of loose parts. The tube support plate displacement system can be used to provide controlled misalignments on one or more tube support plates, in the same or varying amounts and directions, and with one or more apparatus for each individual tube support plate.

    Compact nuclear reactor with integral steam generator

    公开(公告)号:US10803997B2

    公开(公告)日:2020-10-13

    申请号:US15156114

    申请日:2016-05-16

    IPC分类号: G21C1/32 F22B1/02 G21D1/00

    摘要: In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel (12, 14, 16), a nuclear reactor core (10) disposed in the pressure vessel, and a vertically oriented hollow central riser (36) disposed above the nuclear reactor core inside the pressure vessel. A once-through steam generator (OTSG) (30) disposed in the pressure vessel includes vertical tubes (32) arranged in an annular volume defined by the central riser and the pressure vessel. The OTSG further includes a fluid flow volume surrounding the vertical tubes and having a feedwater inlet (50) and a steam outlet (52). The PWR has an operating state in which feedwater injected into the fluid flow volume at the feedwater inlet is converted to steam by heat emanating from primary coolant flowing inside the tubes of the OTSG, and the steam is discharged from the fluid flow volume at the steam outlet.

    Alternating offset U-bend support arrangement

    公开(公告)号:US10902960B2

    公开(公告)日:2021-01-26

    申请号:US16934479

    申请日:2020-07-21

    申请人: BWXT Canada Ltd.

    发明人: Kareem M. A. Aly

    摘要: Arrangement for supporting U-bend tube sections in the high heat environment of steam generators using flat bars. The invention uses a combination of thicker and thinner flat bars to impart a serpentine path to the arc of the normally curvilinear U-tubes. The support system accommodates the dilation and contraction of coolant tubes and other elements caused by the extreme and varying conditions inside a steam generator, and which can cause gaps between coolant tubes and prior art tube support bars. Bars of alternating thickness provide alternating offsets to tensionally push and support each tube on multiple sides and in multiple locations, and this tension keeps the tubes in contact with at least some flat bars on multiple sides regardless of size and shape changes. Support arrangement includes a set of fan bars, each fan bar including thick and thin flat bars projecting up and out from a collector bar.

    TUBE SUPPORT SYSTEM FOR NUCLEAR STEAM GENERATORS

    公开(公告)号:US20170082282A1

    公开(公告)日:2017-03-23

    申请号:US15250513

    申请日:2016-08-29

    申请人: BWXT Canada Ltd.

    摘要: Apparatus for a steam generator that employs tube support plates within a shroud that is in turn disposed within a shell. The tube support plates are made of a material having a coefficient of thermal expansion lower than that of the shroud. The tube support plates are aligned during fabrication, with minimal clearances between components. Using a tube support displacement system, a controlled misalignment is then imposed on one or more tube support plates, as the steam generator heats up. The tube support plate displacement system has only one part, a push rod, which is internal to the steam generator shroud, thereby minimizing the potential of loose parts. The tube support plate displacement system can be used to provide controlled misalignments on one or more tube support plates, in the same or varying amounts and directions, and with one or more apparatus for each individual tube support plate.

    Alternating offset U-bend support arrangement

    公开(公告)号:US11699532B2

    公开(公告)日:2023-07-11

    申请号:US17131922

    申请日:2020-12-23

    申请人: BWXT Canada Ltd.

    发明人: Kareem M. A. Aly

    摘要: Arrangement for supporting U-bend tube sections in the high heat environment of steam generators using flat bars. The invention uses a combination of thicker and thinner flat bars to impart a serpentine path to the arc of the normally curvilinear U-tubes. The support system accommodates the dilation and contraction of coolant tubes and other elements caused by the extreme and varying conditions inside a steam generator, and which can cause gaps between coolant tubes and prior art tube support bars. Bars of alternating thickness provide alternating offsets to tensionally push and support each tube on multiple sides and in multiple locations, and this tension keeps the tubes in contact with at least some flat bars on multiple sides regardless of size and shape changes. Support arrangement includes a set of fan bars, each fan bar including thick and thin flat bars projecting up and out from a collector bar.

    COMPACT NUCLEAR REACTOR WITH INTEGRAL STEAM GENERATOR
    8.
    发明申请
    COMPACT NUCLEAR REACTOR WITH INTEGRAL STEAM GENERATOR 审中-公开
    具有集成蒸汽发生器的紧凑型核反应堆

    公开(公告)号:US20160300628A1

    公开(公告)日:2016-10-13

    申请号:US15156114

    申请日:2016-05-16

    摘要: In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel (12, 14, 16), a nuclear reactor core (10) disposed in the pressure vessel, and a vertically oriented hollow central riser (36) disposed above the nuclear reactor core inside the pressure vessel. A once-through steam generator (OTSG) (30) disposed in the pressure vessel includes vertical tubes (32) arranged in an annular volume defined by the central riser and the pressure vessel. The OTSG further includes a fluid flow volume surrounding the vertical tubes and having a feedwater inlet (50) and a steam outlet (52). The PWR has an operating state in which feedwater injected into the fluid flow volume at the feedwater inlet is converted to steam by heat emanating from primary coolant flowing inside the tubes of the OTSG, and the steam is discharged from the fluid flow volume at the steam outlet.

    摘要翻译: 在说明性实施例中,加压水核反应堆(PWR)包括压力容器(12,14,16),设置在压力容器中的核反应堆芯(10)和设置在压力容器内的垂直取向的中空中心提升管(36) 核反应堆核心在压力容器内。 设置在压力容器中的直通蒸汽发生器(OTSG)(30)包括布置在由中央提升管和压力容器限定的环形容积中的垂直管(32)。 OTSG还包括围绕垂直管并具有给水入口(50)和蒸汽出口(52)的流体流动体积。 PWR具有操作状态,其中通过在OTSG的管内流动的一次冷却剂发出的热量将注入进料水入口处的流体流量的给水转化为蒸汽,并且蒸汽在蒸汽处从流体流量排出 出口。

    ULTRASONIC DEVICE AND METHOD
    9.
    发明申请

    公开(公告)号:US20230131625A1

    公开(公告)日:2023-04-27

    申请号:US17970848

    申请日:2022-10-21

    申请人: BWXT Canada Ltd.

    IPC分类号: G01B17/02

    摘要: An ultrasonic device for scanning an object, the device having a collar configured for coupling to the object, the collar having an arcuate segment, a carriage coupled to the collar, the carriage configured for displacement along the arcuate segment, a ultrasonic probe unit coupled to the collar and comprising a wedge having a contoured face configured for maintaining conforming contact against a surface of the object, the ultrasonic probe unit configured to emit an ultrasonic beam for transmission through the contoured face of the wedge and into the object, and a position locator coupled to the carriage, the position locator configured to record a position of the ultrasonic probe unit.

    Alternating Offset U-Bend Support Arrangement

    公开(公告)号:US20210110943A1

    公开(公告)日:2021-04-15

    申请号:US17131922

    申请日:2020-12-23

    申请人: BWXT Canada Ltd.

    发明人: Kareem M.A. ALY

    摘要: Arrangement for supporting U-bend tube sections in the high heat environment of steam generators using flat bars. The invention uses a combination of thicker and thinner flat bars to impart a serpentine path to the arc of the normally curvilinear U-tubes. The support system accommodates the dilation and contraction of coolant tubes and other elements caused by the extreme and varying conditions inside a steam generator, and which can cause gaps between coolant tubes and prior art tube support bars. Bars of alternating thickness provide alternating offsets to tensionally push and support each tube on multiple sides and in multiple locations, and this tension keeps the tubes in contact with at least some flat bars on multiple sides regardless of size and shape changes. Support arrangement includes a set of fan bars, each fan bar including thick and thin flat bars projecting up and out from a collector bar.