Nuclear reactor control cluster guide device
    21.
    发明授权
    Nuclear reactor control cluster guide device 失效
    核反应堆控制集群指导装置

    公开(公告)号:US5207978A

    公开(公告)日:1993-05-04

    申请号:US762461

    申请日:1991-09-19

    Applicant: Gerard Barbe

    Inventor: Gerard Barbe

    Abstract: A device for guiding a nuclear reactor control cluster comprises guide tubes provided in the fuel assemblies, and in the upper internals, a tubular casing having an upper closure with a hole for passing the cluster drive shaft, horizontal guide plates spaced apart along the casing and cut out so as to let the spider pass and to guide the elements of the cluster, and split tubes for guiding individual elements for protecting the elements from the action of the coolant. Openings are provided immediately below the plates at the top of each internal between the guide plates. The guide tubes in a lower portion of the casing are devoid of openings other than to a slit for passage of a spider carrying the cluster.

    Abstract translation: 用于引导核反应堆控制群的装置包括设置在燃料组件中的引导管,并且在上部内部中具有管状壳体,该管状壳体具有上部封闭件,该封闭件具有用于使簇驱动轴穿过的孔,水平导向板沿壳体间隔开, 切割以使得蜘蛛通过并引导簇的元件,并且分开管以引导各个元件以保护元件免受冷却剂的作用。 在引导板之间的每个内部的顶部的板的正下方提供开口。 壳体下部的引导管没有开口,除了用于携带簇的蜘蛛通过的狭缝之外。

    Method of controlling a pressurized water nuclear reactor
    22.
    发明授权
    Method of controlling a pressurized water nuclear reactor 失效
    控制加压水核反应堆的方法

    公开(公告)号:US5158738A

    公开(公告)日:1992-10-27

    申请号:US435883

    申请日:1989-11-14

    CPC classification number: G21D3/001 G21C7/36 G21D3/08 Y02E30/32 Y02E30/39

    Abstract: A method is disclosed for controlling a PWR comprising a plurality of control bars selectively and individually positioned in the reactor core. The current value of an operating parameter indicative of the power level (for instance the average temperature of the core) is measured as well as the current positions of the control bars and the axial power offset in the core. When the difference between the current value of the operating parameter and the set value exceeds a predetermined deadband interval or the axial power offset in the core exceeds a reference value, the amount by which the reactivity of the core should be modified is computed. Through a simulation process on a model of said reactor, it is determined which ones of the bars may be moved and which are the amounts of travel to be given to the bars for bringing the difference within the deadband and the offset toward the reference value while minimizing a core enthalpy increase factor.

    Abstract translation: 公开了一种用于控制PWR的方法,所述PWR包括多个选择性地且单独地定位在反应堆堆芯中的控制棒。 测量指示功率电平(例如,芯的平均温度)的操作参数的当前值以及控制棒的当前位置和芯中的轴向功率偏移。 当操作参数的当前值与设定值之间的差超过预定的死区间隔或芯中的轴向功率偏移超过参考值时,计算应改变芯的反应性的量。 通过对所述反应器的模型的模拟过程,确定哪些棒可以被移动,并且哪些是给予条的移动量,以使差异在死区内并且偏移朝向参考值,而 使核心焓增加因子最小化。

    High temperature control rod assembly
    23.
    发明授权
    High temperature control rod assembly 失效
    高温控制组件

    公开(公告)号:US5075072A

    公开(公告)日:1991-12-24

    申请号:US419683

    申请日:1989-10-11

    CPC classification number: G21C7/11 Y02E30/39

    Abstract: A high temperature nuclear control rod assembly comprises a plurality of substantially cylindrical segments flexibly joined together in succession by ball joints. The segments are made of a high temperature graphite or carbon-carbon composite. The segment includes a hollow cylindrical sleeve which has an opening for receiving neutron-absorbing material in the form of pellets or compacted rings. The sleeve has a threaded sleeve bore and outer threaded surface. A cylindrical support post has a threaded shaft at one end which is threadably engaged with the sleeve bore to rigidly couple the support post to the sleeve. The other end of the post is formed with a ball portion. A hollow cylindrical collar has an inner threaded surface engageable with the outer threaded surface of the sleeve to rigidly couple the collar to the sleeve. the collar also has a socket portion which cooperates with the ball portion to flexibly connect segments together to form a ball and socket-type joint. In another embodiment, the segment comprises a support member which has a threaded shaft portion and a ball surface portion. The threaded shaft portion is engageable with an inner threaded surface of a ring for rigidly coupling the support member to the ring. The ring in turn has an outer surface at one end which is threadably engageably with a hollow cylindrical sleeve. The other end of the sleeve is formed with a socket portion for engagement with a ball portion of the support member. In yet another embodiment, a secondary rod is slidably inserted in a hollow channel through the center of the segment to provide additional strength. A method for controlling a nuclear reactor utilizing the control rod assembly is also included.

    Abstract translation: 高温核控制杆组件包括多个基本上圆柱形的部分,其通过球接头相继地柔性地连接在一起。 这些段由高温石墨或碳 - 碳复合材料制成。 该段包括中空圆柱形套筒,其具有用于接收颗粒或压实环形式的中子吸收材料的开口。 套筒具有螺纹套筒孔和外螺纹表面。 圆柱形支撑柱在一端具有螺纹轴,该螺纹轴与套筒孔螺纹接合,以将支撑柱刚性地联接到套筒上。 柱的另一端形成有球部。 中空圆柱形套环具有可与套筒的外螺纹表面接合的内螺纹表面,以将套环刚性地联接到套筒。 套环还具有与球部配合以将片段柔性连接在一起以形成球窝型接头的插座部分。 在另一个实施例中,该段包括具有螺纹轴部分和球表面部分的支撑构件。 螺纹轴部分可与环的内螺纹表面接合,用于将支撑构件刚性地联接到环上。 该环又具有一端的外表面,其与中空的圆柱形套筒螺纹接合。 套筒的另一端形成有用于与支撑构件的球部接合的插座部分。 在另一个实施例中,辅助杆可滑动地插入到通过节段的中心的中空通道中以提供额外的强度。 还包括利用控制棒组件控制核反应堆的方法。

    Four pin mounting system for nuclear reactor control rod guide tubes
    24.
    发明授权
    Four pin mounting system for nuclear reactor control rod guide tubes 失效
    用于核反应堆控制杆导管的四针安装系统

    公开(公告)号:US4937039A

    公开(公告)日:1990-06-26

    申请号:US298598

    申请日:1989-01-17

    Abstract: A mounting system for removably mounting the lower flange of the control rod guide tube over an opening in the upper core plate of a nuclear reactor is disclosed. The system includes a pair of resilient pin members and a pair of reinforcing pin members. The resilient pin members are mounted in a passage formed through first opposing sides of the guide tube lower flange. They are resiliently receivable in first bores formed on first opposing sides of the upper core plate to permit deflection thereof when the guide tube is subject to normal shear loads. The resilient pin members bear substantially all of the normal shear load to which the guide tube is subjected. The reinforcing pin members are mounted on the second opposing side of the guide tube lower flange. They are receivable in second bores formed on the second opposing sides of the upper core plate with a clearance. The reinforcing pin members bear substantially all of the abnormal shear load that exceeds the normal shear load. The clearance between the reinforcing pin members and the second bores limits the deflection of the resilient pin members. After the resilient pin members deflect the distance limited by the clearance, the reinforcing pin members bear any additional abnormal shear loads and prevent the additional abnormal shear loads from bearing on the resilient pin members.

    Abstract translation: 公开了一种用于将控制棒引导管的下凸缘可拆卸地安装在核反应堆的上芯板中的开口上的安装系统。 该系统包括一对弹性销构件和一对加强销构件。 弹性销构件安装在通过引导管下凸缘的第一相对侧形成的通道中。 它们可弹性地接收在形成在上芯板的第一相对侧上的第一孔中,以允许当导管受到正常剪切载荷时的挠曲。 弹性销构件承受导管所经受的所有正常剪切载荷。 加强销构件安装在导向管下凸缘的第二相对侧上。 它们可以接收在形成在上芯板的第二相对侧上的第二孔中,具有间隙。 加强销构件基本上承受超过正常剪切载荷的所有异常剪切载荷。 加强销构件和第二孔之间的间隙限制了弹性销构件的偏转。 在弹性销构件偏转由间隙限制的距离之后,加强销构件承受任何额外的异常剪切载荷,并且防止额外的异常剪切载荷承受弹性销构件。

    Resiliently loaded lateral supports for cantilever-mounted rod guides of
a pressurized water reactor
    25.
    发明授权
    Resiliently loaded lateral supports for cantilever-mounted rod guides of a pressurized water reactor 失效
    用于加压水反应堆的悬臂式安装的导杆的弹性加载横向支撑

    公开(公告)号:US4876061A

    公开(公告)日:1989-10-24

    申请号:US236291

    申请日:1988-08-24

    Abstract: A pressurized water reactor of an advanced design comprises, in vertically spaced relationship, a lower barrel assembly having lower and upper core plates, an inner barrel assembly and an axially removable calandria assembly having a lower calandria plate. A plurality of rod guides are cantilever-mounted in parallel axial relationship within the inner barrel assembly and, specifically, are rigidly mounted at the lower ends thereof to the upper core plate. Axially extending sleeves are affixed to the upper ends of the rod guides and telescopingly receive therein generally cylindrical supports which are affixed to and depend downwardly from the lower calandria plate and define alignment axes for the respectively associated rod guides. Links are secured at first ends to the mount and extend radially therefrom at angularly displaced positions, second, free ends of the links being free to move in pivotal rotation from a normal, downward and radially inward position to an upward and radially outward position, when engaged by receiving means formed in the upper ends of the sleeves as the calandria assembly is moved into assembled relationship with the inner barrel assembly. In the assembled relationship, the links, moved fully to the upward and radially outward positions, produce resilient, lateral loading between the respective sleeves and cylindrical mounts and maintain alignment of the associated sleeves and rod guides with the respective alignment axes.

    Abstract translation: 具有先进设计的加压水反应器以垂直间隔的关系包括具有下芯和中芯板的下筒组件,内筒组件和具有较低卡路里板的可轴向移除的加热器组件。 多个杆引导件在内筒组件内以平行轴向的方式悬臂安装,并且具体地,在其下端刚性地安装到上芯板上。 轴向延伸的套筒固定到杆导向件的上端,并且可伸缩地容纳其中的大致圆柱形的支撑件,该支撑件固定到下排气孔板并从其向下并且限定用于相应的杆导向件的对准轴线。 连接件在第一端固定到安装件并且以角度位移的位置径向地延伸,其次,连接件的自由端自由地从正常的,向下的和径向向内的位置移动到向上和径向向外的位置, 当卡拉第里亚组件移动成与内筒组件组装关系时,通过形成在套筒的上端中的接收装置接合。 在组装的关系中,连杆完全移动到向上和径向向外的位置,在相应的套筒和圆柱形安装件之间产生弹性的侧向负载,并且保持相关联的套筒和杆引导件与相应对准轴的对准。

    Ceramic installations
    26.
    发明授权
    Ceramic installations 失效
    陶瓷装置

    公开(公告)号:US4798700A

    公开(公告)日:1989-01-17

    申请号:US5656

    申请日:1987-01-21

    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。

    Manual replacement of old split-pin assemblies by new split-pin
assemblies
    27.
    发明授权
    Manual replacement of old split-pin assemblies by new split-pin assemblies 失效
    通过新的分体销组件手动更换旧的分体销组件

    公开(公告)号:US4756067A

    公开(公告)日:1988-07-12

    申请号:US891016

    申请日:1986-07-31

    Abstract: A replacement station includes an old split-pin-assembly (OSPA) removal stand and a new split-pin-assembly (NSPA) installation stand. The removal stand includes a saw and a drill. With the guide tube to which the OSPA is secured in the removal stand, the saw severs each OSPA below the flange which engages the base of the lower counterbore in the lower guide tube (LGT) separating the OSPA into a pin fragment and a second fragment including the flange and the remainder of the split-pin with the nut threaded into it. The second fragment remains secured to the LGT after the sawing operation. The guide tube is rotated so that the drill is coaxial with the shank of the pin of the second fragment. The second fragment is separated into a third fragment including the flange and a fourth fragment including the remainder of the pin and the nut both removable from the LGT. The installation stand has NSPA blades in which the new split pins are mounted. The LGT sans the OSPA's is positioned on the installation stand. The new nuts are mounted and torqued into the split pins with a long-handled runner and a torque tool permitting a measured torque to be applied to the new nut. Then the cups on the nuts are crimped by a long-handled crimping assembly which has fixed crimping jaws that produce the crimping by moving parallel to the wall of the cup.

    Abstract translation: 更换站包括一个旧的拆卸销组件(OSPA)拆卸支架和一个新的分针销组件(NSPA)安装支架。 拆卸台包括锯和钻。 使用OSPA固定在拆卸支架上的导向管,锯将每个OSPA切割到法兰下方,该凸缘接合下部导管(LGT)中的下沉孔的底部,将OSPA分成销片段和第二片段 包括法兰和分接销的其余部分,螺母拧入其中。 第二个片段在锯切操作后仍然固定在LGT上。 引导管旋转,使得钻头与第二片段的销的柄同轴。 第二片段被分成包括凸缘的第三片段和包括销的剩余部分和螺母的第四片段,两者都可以从LGT移除。 安装支架具有NSPA刀片,其中安装了新的分离销。 LGT无人机OSPA位于安装支架上。 新的螺母通过一个长柄转轮和扭矩工具安装和扭转到分开的销中,允许测量的扭矩施加到新的螺母上。 然后,螺母上的杯子被长柄压接组件卷曲,该组合件具有固定的压接爪,其通过平行于杯的壁移动而产生卷边。

    Tool for cutting locking cups from guide tube mounting screws in a
nuclear reactor
    28.
    发明授权
    Tool for cutting locking cups from guide tube mounting screws in a nuclear reactor 失效
    用于从核反应堆中的导管安装螺钉切割锁定杯的工具

    公开(公告)号:US4690593A

    公开(公告)日:1987-09-01

    申请号:US822182

    申请日:1986-01-24

    Abstract: A cutting tool is manually operable from above the water level in a reactor cavity pool to sever locking cups from the socket-head cap screws which hold guide tubes to the upper support plate of the upper internals of the reactor. The tool includes a support assembly adapted to be mounted on the guide tube. A motor frame is mounted on the support assembly for limited vertical movement with respect thereto and carries a hydraulic motor coupled by a vertically depending shaft to a tubular cutter for rotating same about its axis. The shaft extends through an opening in the support assembly and through a locating tube which surrounds the cutter and is receivable over the associated locking cup when the support assembly is mounted in place. A drive screw is coupled to the frame and to a shaft which extends up to the coupling tube to a manually operable crank to effect vertical movement of the frame and the cutting means coaxially with respect to the locking cup to sever its top wall from its side wall.

    Abstract translation: 切割工具可从反应堆空腔池中的水位上方手动操作,以从将头管固定到反应器的上部内部件的上支撑板的插头头螺钉上切断锁定杯。 该工具包括适于安装在导管上的支撑组件。 马达框架安装在支撑组件上以相对于支撑组件进行有限的垂直运动,并且携带由垂直悬挂的轴联接到管状切割器的液压马达,用于围绕其轴线旋转。 轴延伸穿过支撑组件中的开口并且通过围绕切割器的定位管,并且当支撑组件安装就位时可以将其接收在相关联的锁定杯上方。 驱动螺钉联接到框架和轴,其延伸到联接管到手动操作的曲柄,以实现框架和切割装置相对于锁定杯同轴的垂直运动,以从其侧面切断其顶壁 壁。

    Nuclear power installation with a high temperature pebble bed reactor
    29.
    发明授权
    Nuclear power installation with a high temperature pebble bed reactor 失效
    核电安装用高温卵石床反应堆

    公开(公告)号:US4664871A

    公开(公告)日:1987-05-12

    申请号:US675641

    申请日:1984-11-28

    Inventor: Josef Schoening

    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。

    Releasable anti-ejection device for the control rods of a nuclear reactor
    30.
    发明授权
    Releasable anti-ejection device for the control rods of a nuclear reactor 失效
    用于核反应堆控制棒的可释放的防喷射装置

    公开(公告)号:US4576780A

    公开(公告)日:1986-03-18

    申请号:US486313

    申请日:1983-04-19

    Applicant: Gerard Belz

    Inventor: Gerard Belz

    Abstract: Anti-ejection device for nuclear reactor control rod.The reactor comprises a tight enclosure integral with the nuclear reactor vessel, the control rod being integral with the command bar. A system for manipulating the command bar comprises means for locking it. These means lock the command bar with respect to the tight enclosure for as long as the force exerted on this bar remains below a limit value. This limit value is at least equal to the force exerted on the command bar in the case of an accidental external cause urging the control rod to leave the reactor core. The device comprises means for obtaining a translation of the control rod, by exerting a force exceeding said limit value on the command bar.

    Abstract translation: 用于核反应堆控制棒的防喷器。 反应器包括与核反应堆容器成一体的紧密外壳,控制棒与指挥杆成一体。 用于操纵命令栏的系统包括用于锁定它的装置。 只要施加在该杆上的力保持在极限值以下,这些意味着相对于紧密的外壳锁定命令栏。 该极限值至少等于在意外的外部原因促使控制杆离开反应堆堆芯的情况下施加在指令栏上的力。 该装置包括用于通过在命令条上施加超过所述限制值的力来获得控制杆的平移的装置。

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