专利快速检索-快速检索全球专利，免费商用专利数据库-IPRDB

1. 发明申请

US20160300628A1 COMPACT NUCLEAR REACTOR WITH INTEGRAL STEAM GENERATOR 审中-公开
标题翻译：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
申请人： BWXT Nuclear Energy, Inc. , BWXT Foreign Holdings, LLC , BWXT Canada Ltd.
发明人： Robert T. Fortino , Matthew W. Ales , Nick Idvorian
IPC分类号： G21C1/32 , G21D1/00 , F22B1/02 , G21C19/28
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。

2. 发明授权

US10803997B2 Compact nuclear reactor with integral steam generator 有权
公开(公告)号：US10803997B2
公开(公告)日：2020-10-13
申请号：US15156114
申请日：2016-05-16
申请人： BWXT mPower, Inc. , BWXT Foreign Holdings, LLC , BWXT Canada Ltd.
发明人： Robert T. Fortino , Matthew W. Ales , Nick Idvorian
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.

3. 发明申请

US20160247584A1 SUPPORT STRUCTURE FOR A CONTROL ROD ASSEMBLY OF A NUCLEAR REACTOR 审中-公开
标题翻译：核反应堆控制组件的支撑结构
公开(公告)号：US20160247584A1
公开(公告)日：2016-08-25
申请号：US15147262
申请日：2016-05-05
申请人： BWXT Nuclear Energy, Inc.
发明人： Scott J. Shargots , Matthew W. Ales
IPC分类号： G21C7/08 , G21C21/18
CPC分类号： G21C7/08 , G21C7/117 , G21C7/12 , G21C21/18 , G21Y2002/104 , Y02E30/39
摘要： A control rod guide frame comprises a self supporting stack of two or more columnar elements defining a central passage. The columnar elements may include mating features that mate at abutments between adjacent columnar elements of the stack. The control rod guide frame is suitably used in conjunction with a control rod drive mechanism (CRDM) operatively connected with at least one control rod, and a nuclear reactor core, in which the CRDM moves the at least one control rod into and out of the nuclear reactor core under guidance of the control rod guide frame. In another embodiment, a control rod guide frame comprises a stack of two or more columnar elements defining a central passage having a constant cross-section as a function of position along the central passage. In another embodiment, a control rod guide frame comprises an extruded columnar element providing continuous control rod guidance.
摘要翻译：控制杆引导框架包括限定中心通道的两个或更多个柱状元件的自支撑叠层。柱状元件可以包括在堆叠的相邻柱状元件之间的邻接处配合的配合特征。控制杆引导框架适用于与至少一个控制杆操作连接的控制杆驱动机构（CRDM）和核反应堆堆芯，其中，CRDM将至少一个控制杆移入和移出核反应堆核心在控制杆引导架的引导下。在另一个实施例中，控制杆引导框架包括两个或更多个柱状元件的堆叠，所述柱状元件限定具有作为沿着中心通道的位置的函数的恒定横截面的中心通道。在另一个实施例中，控制杆引导框架包括提供连续控制杆引导的挤压柱状元件。

4. 发明申请

US20220344067A1 SPACE NUCLEAR PROPULSION REACTOR AFT PLENUM ASSEMBLY 有权
公开(公告)号：US20220344067A1
公开(公告)日：2022-10-27
申请号：US17731003
申请日：2022-04-27
申请人： BWXT Nuclear Energy, Inc.
发明人： Matthew W. Ales , Emily D. Fleming , Ted L. Thome
IPC分类号： G21C15/253 , G21C1/32 , G21D5/02
摘要： An aft plenum assembly for use with a nuclear thermal reactor including a pressure vessel and a nozzle assembly having a top plenum plate disposed within the pressure vessel, the top plenum plate defining a first plurality of fuel flow apertures, a bottom plenum plate disposed within the pressure vessel, the bottom plenum plate being parallel to the top plenum plate thereby defining a plenum space therebetween, the bottom plenum plate defining a second plurality of fuel flow apertures, and a plurality of tubular connections extending between the first plurality of fuel flow apertures of the top plenum plate and the second plurality of fuel flow apertures of the bottom plenum plate, wherein the aft plenum assembly is disposed between the pressure vessel and the nozzle assembly.

你已经成功收藏专利！

检索式保存成功!

IPRDB

热门服务

关于我们

友情链接

联系方式