公开(公告)号：US20180261341A1

公开(公告)日：2018-09-13

申请号：US15974888

申请日：2018-05-09

Applicant: BWXT mPower, Inc.

Inventor： Lewis A. Walton ,  George S. Pabis ,  Julius M. Ullmann ,  Jean H. Raas ,  Martha A. Gilliam ,  Anne R. Austin ,  Eric A. Barringer

IPC: G21C13/024 ,  G21C13/02 ,  G21C7/08 ,  G21C1/32 ,  G21C3/33

CPC classification number: G21C13/024 ,  G21C1/32 ,  G21C3/33 ,  G21C7/08 ,  G21C13/02 ,  Y02E30/32 ,  Y02E30/39

Abstract: 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.

公开(公告)号：US20180061511A1

公开(公告)日：2018-03-01

申请号：US15612743

申请日：2017-06-02

Applicant: TerraPower, LLC

Inventor： Peter W. Gibbons ,  Stephen W. Hiller ,  Calen Kaneko ,  Owen Dean Nelson ,  Ashok Odedra ,  P. Harley Park

IPC: G21C7/10 ,  G21C17/04 ,  G21C1/02 ,  G21C19/50 ,  G21C7/32

CPC classification number: G21C7/10 ,  G21C1/026 ,  G21C7/08 ,  G21C7/32 ,  G21C7/34 ,  G21C17/042 ,  G21C19/065 ,  G21C19/07 ,  G21C19/205 ,  G21C19/50 ,  Y02E30/34

Abstract: A rod transfer assembly has an outer rotating plug. A pick-up arm assembly extends from the outer rotating plug and includes a pivoting arm. An inner rotating plug is disposed off-center from and within the outer rotating plug and is rotatable independent of a rotation of the outer rotating plug. An access port rotating plug is disposed off-center from and within the inner rotating plug and is rotatable independent of rotation of the outer and inner rotating plugs. A pull arm extends from the access port rotating plug.

公开(公告)号：US09905321B2

公开(公告)日：2018-02-27

申请号：US14005065

申请日：2012-03-15

Applicant: Alain Grossetete

Inventor： Alain Grossetete

IPC: G21C7/08 ,  G21D3/00 ,  G21C7/22 ,  G21D3/10 ,  G21D3/16

CPC classification number: G21D3/001 ,  G21C7/08 ,  G21C7/22 ,  G21D3/10 ,  G21D3/16 ,  Y02E30/32 ,  Y02E30/39

Abstract: 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).

公开(公告)号：US09721681B2

公开(公告)日：2017-08-01

申请号：US13863659

申请日：2013-04-16

Applicant: Babcock & Wilcox mPower, Inc.

Inventor： Scott J Shargots ,  Matthew W Ales ,  Michael S Berthold

IPC: G21C1/32 ,  G21C7/08 ,  G21C7/12 ,  G21C13/02 ,  G21C19/19

CPC classification number: G21C7/08 ,  G21C1/322 ,  G21C7/12 ,  G21C13/02 ,  G21C19/19 ,  Y02E30/32 ,  Y02E30/39

Abstract: 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.

公开(公告)号：US09640283B2

公开(公告)日：2017-05-02

申请号：US14291890

申请日：2014-05-30

Applicant: Advanced Reactor Concepts LLC

Inventor： Leon C. Walters

IPC: G21C1/02 ,  G21C9/027 ,  G21C19/20 ,  G21C7/08 ,  G21C5/06 ,  G21C1/00

CPC classification number: G21C1/02 ,  G21C5/06 ,  G21C7/08 ,  G21C9/027 ,  G21C19/205 ,  Y02E30/34 ,  Y02E30/39

Abstract: 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.

公开(公告)号：US20160329116A1

公开(公告)日：2016-11-10

申请号：US14005065

申请日：2012-03-15

Applicant: Alain GROSSETETE

Inventor： Alain GROSSETETE

IPC: G21D3/00 ,  G21D3/16 ,  G21D3/10 ,  G21C7/08 ,  G21C7/22

CPC classification number: G21D3/001 ,  G21C7/08 ,  G21C7/22 ,  G21D3/10 ,  G21D3/16 ,  Y02E30/32 ,  Y02E30/39

Abstract: 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).

Abstract translation: 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。

公开(公告)号：US20150243377A1

公开(公告)日：2015-08-27

申请号：US14665341

申请日：2015-03-23

Applicant: Babcock & Wilcox Nuclear Energy, Inc.

Inventor： John D. Malloy ,  Mathew W. Ales

IPC: G21C1/32 ,  G21C1/08 ,  G21C7/08

CPC classification number: G21C1/322 ,  G21C1/086 ,  G21C7/08 ,  G21C15/243 ,  Y02E30/32 ,  Y02E30/39

Abstract: 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

Abstract translation: 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

公开(公告)号：US20140368219A1

公开(公告)日：2014-12-18

申请号：US13920649

申请日：2013-06-18

Applicant: Analysis and Measurement Services Corporation

Inventor： Gregory W. Morton ,  Samuel D. Caylor ,  Jacob R. McCulley ,  Hashem M. Hashemian

IPC: G01R27/26

CPC classification number: G21C7/08 ,  G21C7/12 ,  G21C7/18 ,  G21C7/36 ,  G21C17/00 ,  Y02E30/39

Abstract: Systems and methods of monitoring a rod control system of a nuclear power plant, including calculating impedance of at least one coil of a rod movement mechanism non-intrusively while the system is operating, comparing a measured impedance to a reference impedance, and determining if the measured impedance deviates from the reference impedance value by a predetermined amount to indicate degradation of the rod control system.

Abstract translation: 监测核电站的杆控制系统的系统和方法，包括在系统运行时非侵入地计算杆运动机构的至少一个线圈的阻抗，将测得的阻抗与参考阻抗进行比较，以及确定是否 测量的阻抗偏离参考阻抗值预定量，以指示杆控制系统的劣化。

公开(公告)号：US20140133619A1

公开(公告)日：2014-05-15

申请号：US13863901

申请日：2013-04-16

Applicant: Babcock & Wilcox mPower, Inc.

Inventor： Vince J. Bilovsky

IPC: G21C7/00

CPC classification number: G21C7/00 ,  G21C1/322 ,  G21C3/326 ,  G21C3/3262 ,  G21C5/18 ,  G21C7/04 ,  G21C7/08 ,  G21D3/08 ,  Y02E30/32 ,  Y02E30/38 ,  Y02E30/39

Abstract: A pressurized water reactor (PWR) includes a pressure vessel containing a nuclear reactor core immersed in primary coolant water, control rod assemblies (CRA's), and control rod drive mechanisms (CRDM's) operating the CRA's. The reactor core has axially varying 235U enrichment and/or axially varying burnable poison concentration. A CRDM controller controls the CRA's over a burn-up cycle that does not include fuel assembly shuffling and is divided into a plurality of burn-up intervals. The CRDM controller is configured to, for each burn up interval: position the CRA's in accordance with a CRA pattern defining a set of fixed positions for the CRA's except for a sub-set of CRA's designated by the CRA pattern as floating CRA's, and control power level of the PWR by adjusting the floating CRA's without not adjusting the CRA's not designated as floating CRA's. The primary coolant water optionally does not contain soluble neutron poison.

Abstract translation: 加压水反应堆（PWR）包括一个压力容器，该压力容器含有沉积在一次冷却水中的核反应堆堆芯，控制杆组件（CRA）和操作CRA的控制杆驱动机构（CRDM）。 反应堆芯具有轴向变化的235U富集和/或轴向变化的可燃毒物浓度。 CRDM控制器在不包括燃料组装洗牌的燃尽循环中控制CRA，并且被分为多个燃烧间隔。 CRDM控制器被配置为对于每个燃烧间隔：将CRA定位为根据CRA模式定位CRA模式，该CRA模式为CRA定义一组固定位置，除了由CRA模式指定的CRA子集作为浮动CRA，并且控制 通过调整浮动CRA而不调整未指定为浮动CRA的CRA，PWR的功率级别。 主冷却水任选地不含有可溶性中子毒素。

公开(公告)号：US08699653B2

公开(公告)日：2014-04-15

申请号：US13279596

申请日：2011-10-24

Applicant: Keith J. Drudy ,  Norman P. Mueller ,  Elijah A. Richter

Inventor： Keith J. Drudy ,  Norman P. Mueller ,  Elijah A. Richter

IPC: G21C7/117 ,  G21C7/08 ,  G21C7/36 ,  G21C7/00

CPC classification number: G21C7/08 ,  G21D3/001 ,  Y02E30/39

Abstract: 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.

Abstract translation: 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。