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1. 发明授权

US10109379B2 Control rod guide tube with an extended intermediate guide assembly 有权
公开(公告)号：US10109379B2
公开(公告)日：2018-10-23
申请号：US14295521
申请日：2014-06-04
申请人： Westinghouse Electric Company LLC
发明人： Vytautas J. Mickus , Ibrahim M. Ezzi
IPC分类号： G21C7/117 , G21C7/08
摘要： A nuclear reactor having an upper internals control rod assembly guide tube formed from upper and lower sections that are connected along a central axial region of the guide tube at an intermediate coupling. An extended control rod axial support is provided for at least some of the control rods over a finite distance within at least one of the interiors of the lower guide tube section or the upper guide tube section.

2. 发明申请

US20180261341A1 SMALL MODULAR REACTOR FUEL ASSEMBLY 审中-公开
公开(公告)号：US20180261341A1
公开(公告)日：2018-09-13
申请号：US15974888
申请日：2018-05-09
申请人： BWXT mPower, Inc.
发明人： Lewis A. Walton , George S. Pabis , Julius M. Ullmann , Jean H. Raas , Martha A. Gilliam , Anne R. Austin , Eric A. Barringer
IPC分类号： G21C13/024 , G21C13/02 , G21C7/08 , G21C1/32 , G21C3/33
CPC分类号： G21C13/024 , G21C1/32 , G21C3/33 , G21C7/08 , G21C13/02 , Y02E30/32 , Y02E30/39
摘要： A pressurized water reactor (PWR) comprises a pressure vessel containing primary coolant water. A nuclear reactor core is disposed in the pressure vessel and includes a plurality of fuel assemblies. Each fuel assembly includes a plurality of fuel rods containing a fissile material. A control system includes a plurality of control rod assemblies (CRA's). Each CRA is guided by a corresponding CRA guide structure. A support element is disposed above the CRA guide structures and supports the CRA guide structures. The pressure vessel may be cylindrical, and the support element may comprise a support plate having a circular periphery supported by the cylindrical pressure vessel. The CRA guide structures suitably hang downward from the support plate. The lower end of each CRA guide structure may include alignment features that engage corresponding alignment features of the upper end of the corresponding fuel assembly.

3. 发明授权

US09905321B2 Method for operating a pressurized water reactor during load monitoring 有权
公开(公告)号：US09905321B2
公开(公告)日：2018-02-27
申请号：US14005065
申请日：2012-03-15
申请人： Alain Grossetete
发明人： Alain Grossetete
IPC分类号： G21C7/08 , G21D3/00 , G21C7/22 , G21D3/10 , G21D3/16
CPC分类号： G21D3/001 , G21C7/08 , G21C7/22 , G21D3/10 , G21D3/16 , Y02E30/32 , Y02E30/39
摘要： The present invention relates to a method for controlling a pressurized water reactor (100) comprising the steps that involve measuring the effective power (Pe) of the nuclear reactor; acquiring a reference value for the desired power (Pc); acquiring an estimated duration (DURATION) for the increase in power in order to achieve said reference value of the target power (Pc) desired, said estimated duration (DURATION) corresponding to the time taken for the power to increase from said effective power (Pe) to said reference value for the target power (Pc); determining the reference position (Z) of at least one control rod cluster among said plurality of control rod clusters (40) in order to achieve said reference value for said target power (Pc) desired as a function of said estimated duration (DURATION), of said measured effective power (Pe) and of said reference value for said target power (Pc); monitoring the position of said at least one control rod cluster so as to position it in its reference position (Z).

4. 发明授权

US09721681B2 Integral pressurized water reactor with compact upper internals assembly 有权
公开(公告)号：US09721681B2
公开(公告)日：2017-08-01
申请号：US13863659
申请日：2013-04-16
申请人： Babcock & Wilcox mPower, Inc.
发明人： Scott J Shargots , Matthew W Ales , Michael S Berthold
IPC分类号： G21C1/32 , G21C7/08 , G21C7/12 , G21C13/02 , G21C19/19
CPC分类号： G21C7/08 , G21C1/322 , G21C7/12 , G21C13/02 , G21C19/19 , Y02E30/32 , Y02E30/39
摘要： An integral pressurized water reactor (PWR) comprises: a cylindrical pressure vessel including an upper vessel section and a lower vessel section joined by a mid-flange; a cylindrical central riser disposed concentrically inside the cylindrical pressure vessel and including an upper riser section disposed in the upper vessel section and a lower riser section disposed in the lower vessel section; steam generators disposed inside the cylindrical pressure vessel in the upper vessel section; a reactor core comprising fissile material disposed inside the cylindrical pressure vessel in the lower vessel section; and control rod drive mechanism (CRDM) units disposed inside the cylindrical pressure vessel above the reactor core and in the lower vessel section. There is no vertical overlap between the steam generators and the CRDM units.

5. 发明授权

US09640283B2 Small, fast neutron spectrum nuclear power plant with a long refueling interval 有权
公开(公告)号：US09640283B2
公开(公告)日：2017-05-02
申请号：US14291890
申请日：2014-05-30
申请人： Advanced Reactor Concepts LLC
发明人： Leon C. Walters
IPC分类号： G21C1/02 , G21C9/027 , G21C19/20 , G21C7/08 , G21C5/06 , G21C1/00
CPC分类号： G21C1/02 , G21C5/06 , G21C7/08 , G21C9/027 , G21C19/205 , Y02E30/34 , Y02E30/39
摘要： Nuclear reactor systems and methods are described having many unique features tailored to address the special conditions and needs of emerging markets. The fast neutron spectrum nuclear reactor system may include a reactor having a reactor tank. A reactor core may be located within the reactor tank. The reactor core may include a fuel column of metal or cermet fuel using liquid sodium as a heat transfer medium. A pump may circulate the liquid sodium through a heat exchanger. The system may include a balance of plant with no nuclear safety function. The reactor may be modular, and may produce approximately 100 MWe.

6. 发明申请

US20160365161A1 NON-INTRUSIVE ERROR DETECTION TECHNIQUES FOR CONTROL AND SHUTDOWN ROD POSITION IN NUCLEAR REACTORS 审中-公开
标题翻译：核反应堆控制和关闭位置的非侵入式错误检测技术
公开(公告)号：US20160365161A1
公开(公告)日：2016-12-15
申请号：US15247169
申请日：2016-08-25
申请人： Samuel Caylor , Hashem M. Hashemian , Gregory W. Morton
发明人： Samuel Caylor , Hashem M. Hashemian , Gregory W. Morton
IPC分类号： G21C17/12 , G21D3/00 , G21C7/08
CPC分类号： G21C7/36 , G21C7/10 , G21C17/00 , G21C17/12 , G21D3/001 , Y02E30/40
摘要： Non-intrusive error detection techniques for control and shutdown rod position in nuclear reactors, including methods of monitoring digital rod position indication (DRPI) signals of a DRPI system of a nuclear power plant. The methods include acquiring digital rod position signals at a point between a DRPI display cabinet and a DRPI data cabinet of the DRPI system, and processing the digital rod position signals to identify variations in a signal level and a signal timing of the digital rod position signals to determine rod position errors of the DRPI system.
摘要翻译：用于控制和关闭核反应堆中的杆位置的非侵入式误差检测技术，包括监测核电站DRPI系统的数字杆位置指示（DRPI）信号的方法。这些方法包括在DRPI显示柜和DRPI系统的DRPI数据柜之间的点处获取数字杆位置信号，以及处理数字杆位置信号，以识别数字杆位置信号的信号电平和信号定时的变化以确定DRPI系统的杆位置误差。

7. 发明申请

US20160329116A1 METHOD FOR OPERATING A PRESSURIZED WATER REACTOR DURING LOAD MONITORING 有权
标题翻译：负荷监测期间加压水反应器的运行方法
公开(公告)号：US20160329116A1
公开(公告)日：2016-11-10
申请号：US14005065
申请日：2012-03-15
申请人： Alain GROSSETETE
发明人： Alain GROSSETETE
IPC分类号： G21D3/00 , G21D3/16 , G21D3/10 , G21C7/08 , G21C7/22
CPC分类号： G21D3/001 , G21C7/08 , G21C7/22 , G21D3/10 , G21D3/16 , Y02E30/32 , Y02E30/39
摘要： The present invention relates to a method for controlling a pressurized water reactor (100) comprising the steps that involve measuring the effective power (Pe) of the nuclear reactor; acquiring a reference value for the desired power (Pc); acquiring an estimated duration (DURATION) for the increase in power in order to achieve said reference value of the target power (Pc) desired, said estimated duration (DURATION) corresponding to the time taken for the power to increase from said effective power (Pe) to said reference value for the target power (Pc); determining the reference position (Z) of at least one control rod cluster among said plurality of control rod clusters (40) in order to achieve said reference value for said target power (Pc) desired as a function of said estimated duration (DURATION), of said measured effective power (Pe) and of said reference value for said target power (Pc); monitoring the position of said at least one control rod cluster so as to position it in its reference position (Z).
摘要翻译：本发明涉及一种用于控制压水反应堆（100）的方法，包括测量核反应堆的有效功率（Pe）的步骤; 获取所需功率（Pc）的参考值; 获取用于增加功率的估计持续时间（DURATION），以实现所需目标功率（Pc）的所述参考值，所述估计持续时间（DURATION）对应于从所述有效功率增加功率所花费的时间（Pe ）到目标功率（Pc）的所述参考值; 确定所述多个控制棒簇（40）中的至少一个控制棒簇的参考位置（Z），以便根据所述估计持续时间（DURATION）达到所需要的所述目标功率（Pc）的所述参考值，的所述测量有效功率（Pe）和所述目标功率（Pc）的所述参考值; 监视所述至少一个控制棒组的位置，以将其定位在其参考位置（Z）中。

8. 发明申请

US20150243377A1 COMPACT NUCLEAR REACTOR 审中-公开
标题翻译：紧凑型核反应堆
公开(公告)号：US20150243377A1
公开(公告)日：2015-08-27
申请号：US14665341
申请日：2015-03-23
申请人： Babcock & Wilcox Nuclear Energy, Inc.
发明人： John D. Malloy , Mathew W. Ales
IPC分类号： G21C1/32 , G21C1/08 , G21C7/08
CPC分类号： G21C1/322 , G21C1/086 , G21C7/08 , G21C15/243 , Y02E30/32 , Y02E30/39
摘要： A pressurized water nuclear reactor (PWR) includes a once through steam generator (OTSG) disposed in a generally cylindrical pressure vessel and a divider plate spaced apart from the open end of a central riser. A sealing portion of the pressure vessel and the divider plate define an integral pressurizer volume that is separated by the divider plate from the remaining interior volume of the pressure vessel. An internal control rod drive mechanism (CRDM) has all mechanical and electromagnetomotive components including at least a motor and a lead screw disposed inside the pressure vessel. Optionally CRDM units are staggered at two or more different levels such that no two neighboring CRDM units are at the same level. Internal primary coolant pumps have all mechanical and electromagnetomotive components including at least a motor and at least one impeller disposed inside the pressure vessel. Optionally, the pumps and/or CRDM are arranged below the OTSG
摘要翻译：加压水核反应堆（PWR）包括设置在大致圆柱形的压力容器中的一次性蒸汽发生器（OTSG）和与中央提升管的开口端间隔开的分隔板。压力容器和分隔板的密封部分限定了由分隔板与压力容器的剩余内部容积隔开的整体加压器体积。内部控制杆驱动机构（CRDM）具有至少包括设置在压力容器内部的电动机和导螺杆的所有机械和电动汽车部件。可选地，CRDM单元在两个或更多个不同级别交错，使得没有两个相邻的CRDM单元处于相同的水平。内部主冷却剂泵具有所有机械和电动汽车部件，其包括至少一个电动机和至少一个设置在压力容器内的叶轮。可选地，泵和/或CRDM布置在OTSG的下方

9. 发明授权

US08699653B2 Method of achieving automatic axial power distribution control 有权
标题翻译：实现自动轴向配电控制的方法
公开(公告)号：US08699653B2
公开(公告)日：2014-04-15
申请号：US13279596
申请日：2011-10-24
申请人： Keith J. Drudy , Norman P. Mueller , Elijah A. Richter
发明人： Keith J. Drudy , Norman P. Mueller , Elijah A. Richter
IPC分类号： G21C7/117 , G21C7/08 , G21C7/36 , G21C7/00
CPC分类号： G21C7/08 , G21D3/001 , Y02E30/39
摘要： A control strategy for a pressurized water nuclear reactor that employs separate, independent control rod banks for respectively controlling Tavg and axial offset within corresponding deadbands. The strategy does not permit the control banks controlling reactor core power and the control banks controlling axial offset to move together, but normally gives preference to the control banks controlling the Tavg except when a demand signal is received simultaneously by both independent control rod banks to move in a same direction, in which case, the control bank compensating for the axial offset is given preference.
摘要翻译：压力水核反应堆的控制策略采用独立的，独立的控制棒组，分别控制相应死区内的Tavg和轴向偏移。该策略不允许控制反应堆堆芯功率的控制组和控制轴偏移的控制组一起移动，但通常优先控制控制组件的控制组，除非同时由独立的控制棒组移动需求信号在相同的方向上，在这种情况下，给予偏置轴偏移的控制组。

10. 发明授权

US08537962B1 Advanced gray rod control assembly 有权
标题翻译：高级灰棒控制组件
公开(公告)号：US08537962B1
公开(公告)日：2013-09-17
申请号：US12028119
申请日：2008-02-08
申请人： Keith J. Drudy , William R. Carlson , Michael E. Conner , Mark Goldenfield , Michael J. Hone , Carroll J. Long, Jr. , Jerod Parkinson , Radu O. Pomirleanu
发明人： Keith J. Drudy , William R. Carlson , Michael E. Conner , Mark Goldenfield , Michael J. Hone , Carroll J. Long, Jr. , Jerod Parkinson , Radu O. Pomirleanu
IPC分类号： G21C7/08 , G21C7/10 , G21C7/103
CPC分类号： G21C7/10 , G21Y2002/201 , G21Y2002/304 , G21Y2004/10 , G21Y2004/30 , Y02E30/39
摘要： An advanced gray rod control assembly (GRCA) for a nuclear reactor. The GRCA provides controlled insertion of gray rod assemblies into the reactor, thereby controlling the rate of power produced by the reactor and providing reactivity control at full power. Each gray rod assembly includes an elongated tubular member, a primary neutron-absorber disposed within the tubular member said neutron-absorber comprising an absorber material, preferably tungsten, having a 2200 m/s neutron absorption microscopic capture cross-section of from 10 to 30 barns. An internal support tube can be positioned between the primary absorber and the tubular member as a secondary absorber to enhance neutron absorption, absorber depletion, assembly weight, and assembly heat transfer characteristics.
摘要翻译：用于核反应堆的先进的灰棒控制组件（GRCA）。 GRCA提供将灰棒组件控制插入反应器，从而控制由反应器产生的功率的速率并在全功率下提供反应性控制。每个灰色杆组件包括细长管状构件，设置在管状构件内的初级中子吸收器，所述中子吸收器包括吸收材料，优选为钨，具有10至30的2200m / s中子吸收微观捕获横截面谷仓内部支撑管可以位于主吸收器和管状构件之间，作为二次吸收器，以增强中子吸收，吸收剂消耗，组装重量和组装传热特性。

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