公开(公告)号：US20230282376A1

公开(公告)日：2023-09-07

申请号：US17685324

申请日：2022-03-02

Applicant: Thomas J. Wielenga

Inventor： Thomas J. Wielenga

IPC: G21C7/22 ,  G21C3/54 ,  G21C15/02

CPC classification number: G21C7/22 ,  G21C3/54 ,  G21C15/02

Abstract: A nuclear reactor controlled by moving a liquid fuel between a reservoir and chambers in the core is provided. No pumps or moving parts within the reactor vessel are needed to move the fuel. The control system moves the liquid fuel between the core and the reservoir by moving a separate control gas. It can monitor the internal state of the core through the control connections. The fuel chamber is shaped so that evolved gases escape the core and can be collected at the control connections. The core reverts to a safe state on power failure.

公开(公告)号：US20230260668A1

公开(公告)日：2023-08-17

申请号：US18044479

申请日：2021-09-01

Applicant: Ian Richard SCOTT

Inventor： Ian Richard SCOTT

IPC: G21C15/26 ,  G21C1/24 ,  G21C7/32 ,  G21C15/247 ,  G21C3/54 ,  G21C7/22

CPC classification number: G21C15/26 ,  G21C1/24 ,  G21C3/54 ,  G21C7/22 ,  G21C7/32 ,  G21C15/247

Abstract: A passive nuclear reactor control device. The passive nuclear reactor control device comprises a sealed chamber, which comprises a reservoir and a tube in fluid communication with the reservoir. A molten salt is within the sealed chamber, the molten salt being a eutectic mixture of a monovalent metal halide, and a fluoride or chloride of one or more lanthanides and/or a luoride or chloride of hafnium. A gas is within the sealed chamber, and the gas does not react with the molten salt.

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：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：US20050283553A1

公开(公告)日：2005-12-22

申请号：US10970570

申请日：2004-10-21

Applicant: Gregory Droba

Inventor： Gregory Droba

IPC: G06F11/00 ,  G06F12/14 ,  G21C7/22 ,  G21C17/02 ,  H03M1/78

CPC classification number: G05B19/0426 ,  G05B2219/23267 ,  G05B2219/25278 ,  G05B2219/25416 ,  G06F9/4825 ,  G21C7/22 ,  G21C17/00 ,  G21D3/00 ,  Y02E30/39

Abstract: A method for operating a controller having a number of timers to thereby control a plurality of events greater than the number of timers, includes, between clock ticks, receiving one or more signals from sensors, switches, executing programs, or a combination therefore that initiate one or more timed events. After a clock tick immediately following the receiving of the one or more signals, the method further includes updating entries in an event control block in accordance with the received signal or signals. The entries include a time remaining for pending events, a time past due for active events, and a priority of each event. The method further includes determining whether any pending event or events have timed out, activating any timed out events, and sending a signal notifying an executing program of the activated event having the highest priority.

Abstract translation: 一种用于操作具有多个定时器以由此控制大于定时器数量的多个事件的控制器的方法，包括在时钟脉冲之间，从传感器接收一个或多个信号，切换，执行程序或由此启动的组合 一个或多个定时事件。 在接收到一个或多个信号之后立即刻刻时钟之后，该方法还包括根据接收的信号或信号来更新事件控制​​块中的条目。 这些条目包括待处理事件的剩余时间，活动事件的过去时间以及每个事件的优先级。 该方法还包括确定任何未决事件或事件是否已超时，激活任何超时事件，以及发送通知执行程序的具有最高优先级的激活事件的信号。

公开(公告)号：US20050281368A1

公开(公告)日：2005-12-22

申请号：US10872205

申请日：2004-06-18

Applicant: Gregory Droba ,  Stanley Frederick

Inventor： Gregory Droba ,  Stanley Frederick

IPC: G06F11/00 ,  G06F12/14 ,  G21C7/22 ,  G21C17/02 ,  H03M1/78

CPC classification number: G05B19/058 ,  G21C7/22 ,  G21C17/02 ,  G21Y2002/206 ,  G21Y2004/40 ,  Y02E30/39

Abstract: A method and system is provided for a nuclear reactor safety related application. The method includes executing two forms of a same application-specific logic, one of the two forms implemented as hardware logic, and the other of the two forms implemented as software instructions for execution by microprocessor-based controlling software. Each form of the application-specific logic is executed with a same set of inputs. The method compares a result produced from the execution of the hardware-implemented form to a result produced from the execution of the software-implemented form. When the compared results concur, the controlling software performs actions associated with the concurring results by executing microprocessor-based software. When the compared results fail to concur, the controlling software reports the failure of the compared results to concur to an operator by executing microprocessor-based software, and thereafter places the microprocessor-based software system into an inoperative (INOP) mode.

Abstract translation: 为核反应堆安全相关应用提供了一种方法和系统。 该方法包括执行相同的应用程序特定逻辑的两种形式，作为硬件逻辑实现的两种形式中的一种形式，以及作为用于由基于微处理器的控制软件执行的软件指令实现的两种形式中的另一种形式。 应用程序特定逻辑的每种形式都使用相同的输入集执行。 该方法将从执行硬件实现的形式产生的结果与由执行软件实现的形式产生的结果进行比较。 当比较结果一致时，控制软件通过执行基于微处理器的软件来执行与同步结果相关的动作。 当比较结果不符合要求时，控制软件通过执行基于微处理器的软件报告比较结果的失败，同时使操作者同时进行，然后将基于微处理器的软件系统置于无效（INOP）模式。

公开(公告)号：US5271052A

公开(公告)日：1993-12-14

申请号：US2561

申请日：1993-01-11

Applicant: Albert J. Impink, Jr. ,  Joseph A. Battaglia ,  John W. Fasnacht ,  George G. Konopka

Inventor： Albert J. Impink, Jr. ,  Joseph A. Battaglia ,  John W. Fasnacht ,  George G. Konopka

IPC: G21C7/22 ,  G21C9/033 ,  G21C7/00

CPC classification number: G21C7/22 ,  G21Y2002/103 ,  G21Y2004/10 ,  Y02E30/39

Abstract: A nuclear reactor plant is provided in which the reactor coolant system contains a dissolved solution of enriched boric acid. The boron-10 to boron-11 atomic isotope ratio of the enriched boric acid solution is greater than 30:70 at the start of the reactor core cycle. The nuclear reactor plant design provides for minimal mixing between the reactor coolant solution containing the enriched boric acid solution and the natural boric acid solution used during refueling operations.

Abstract translation: 提供了一种核反应堆设备，其中反应堆冷却剂系统含有溶解的富硼酸溶液。 在反应堆核心循环开始时，富硼酸溶液的硼-10至硼-11原子同位素比大于30:70。 核反应堆设备提供了包含富硼酸溶液的反应堆冷却剂溶液与加油操作中使用的天然硼酸溶液之间的最小混合。

公开(公告)号：US4798700A

公开(公告)日：1989-01-17

申请号：US5656

申请日：1987-01-21

Applicant: Claus Elter ,  Edgar Hornischer ,  Herrmann Schmitt ,  Josef Schoening

Inventor： Claus Elter ,  Edgar Hornischer ,  Herrmann Schmitt ,  Josef Schoening

IPC: G21C5/04 ,  G21C7/107 ,  G21C11/06 ,  G21C7/08 ,  G21C7/22

CPC classification number: G21C5/04 ,  G21C11/06 ,  G21C7/107 ,  G21Y2002/204 ,  G21Y2004/10 ,  G21Y2004/30 ,  Y02E30/33 ,  Y02E30/39

Abstract: A gas-cooled high temperature reactor is provided having a core filled with spherical fuel elements, in combination with a graphite side reflector including at least one nose-like projection protruding radially into the reactor core from said graphite said reflector, the at least one nose-like projection including at least one vertically disposed cavity adapted to receive discrete absorber material elements introduced into said reactor core as well as a vertically disposed continuous opening which permits communication between said cavity and the core of the reactor, said opening having a maximum width adjacent said cavity which is less than the minimum dimension of said discrete absorber material elements in order to prevent passage of said elements into said continuous opening from said cavity.

Abstract translation: 提供了一种气体冷却的高温反应器，其具有填充有球形燃料元件的核心，与石墨侧反射器组合，该石墨侧反射器包括从所述石墨反射器径向突出到反应堆芯中的至少一个鼻状突起，所述至少一个鼻 类似的突起包括至少一个垂直设置的腔，其适于接收引入到所述反应堆芯中的不连续的吸收体材料元件以及允许所述空腔与所述反应器的芯之间连通的垂直设置的连续开口，所述开口具有相邻的最大宽度 所述空腔小于所述离散吸收体材料元件的最小尺寸，以便防止所述元件从所述空腔通入所述连续开口。

公开(公告)号：US4664871A

公开(公告)日：1987-05-12

申请号：US675641

申请日：1984-11-28

Applicant: Josef Schoening

Inventor： Josef Schoening

IPC: G21C1/07 ,  G21C7/08 ,  G21C11/06 ,  G21C7/22 ,  G21C15/18

CPC classification number: G21C1/07 ,  G21C11/06 ,  G21C7/08 ,  G21Y2002/201 ,  G21Y2002/301 ,  G21Y2004/305 ,  Y02E30/36 ,  Y02E30/39

Abstract: Disclosed is a nuclear power plant comprising a high-temperature pebble bed reactor contained in a cylindrical steel pressure vessel in which an upper part of the cylindrical steel pressure vessel, which contains a heat utilization system, is retracted and equipped with a cover upon which circulating blowers are placed. The heat utilization system comprises, in a known manner, a single steam generator. The steam generator comprises at least two sub-systems independent of one another, with their own distributors and collectors, and with their own inlet and outlet lines. A first shut-down arrangement comprises a plurality of absorber rods insertable into bores of the side reflector from above and comprises rod drives arranged outside the steel pressure vessel in the area of its retracted upper part. A second shut-down arrangement comprises small absorber spheres for introducing into the core of the reactor, and several storage containers and annular conduits for said spheres. The storage containers are also arranged outside the steel pressure vessel in the area of its retracted upper part. Annular conduits for the introduction of the small absorber sphere are, however, disposed inside the steel pressure vessel and connected with channels provided in projections of the side reflector protruding into the core.

Abstract translation: 公开了一种核电站，其包括在圆筒形钢压力容器中的高温卵石床反应器，其中包含热利用系统的圆柱形钢压力容器的上部被缩回并装有盖，循环 鼓风机被放置。 热利用系统以已知的方式包括单个蒸汽发生器。 蒸汽发生器包括彼此独立的至少两个子系统，具有它们自己的分配器和收集器以及它们自己的入口和出口管线。 第一关闭装置包括从上方可插入侧反射器的孔中的多个吸收器杆，并且包括在其缩回的上部区域中布置在钢压力容器外部的杆驱动器。 第二关闭装置包括用于引入反应器的核心的小吸收器球体，以及用于所述球体的几个储存容器和环形管道。 储存容器也在其缩回的上部区域中布置在钢压力容器的外部。 然而，用于引入小吸收器球的环形导管设置在钢压力容器内，并且与设置在突出到芯中的侧反射体的突起中的通道连接。

公开(公告)号：US4032401A

公开(公告)日：1977-06-28

申请号：US494431

申请日：1974-08-02

Applicant: Reinhard Froelich ,  Howard W. Yant

Inventor： Reinhard Froelich ,  Howard W. Yant

IPC: G21C7/06 ,  G21C7/22

CPC classification number: G21C7/22 ,  G21C7/06 ,  Y02E30/39

Abstract: A control system for a nuclear reactor comprising hollow mechanically operated control rods and a liquid neutron absorber which may be circulated through the hollow control rods. The liquid neutron absorber provides the nuclear reactor with a redundant safety system to deactivate the reactor.