Parallel flow collar for reducing vibration of a rod within a diffuser
    1.
    发明授权
    Parallel flow collar for reducing vibration of a rod within a diffuser 失效
    用于减少扩散器内的杆的振动的平行流动环

    公开(公告)号:US4270979A

    公开(公告)日:1981-06-02

    申请号:US970694

    申请日:1978-12-18

    申请人: Frank Bevilacqua

    发明人: Frank Bevilacqua

    IPC分类号: G21C3/322 G21C3/30 G21C7/08

    CPC分类号: G21C3/322 Y02E30/38

    摘要: The oscillatory forces acting on an eccentric rod within a diffuser are reduced by an annular bypass collar around the rod immediately upstream of the diffuser region. The collar includes a sleeve portion that completely surrounds the rod and a bypass channel outside the sleeve which carries most of the fluid into the diffuser region on a path parallel to but spaced from the rod. The collar is most effective when a multiplicity of discrete bypass channels are provided.

    摘要翻译: 作用在扩散器内的偏心杆上的振荡力通过紧邻扩散器区域上游的杆的环形旁路环来减小。 套环包括完全围绕杆的套筒部分和在套筒外部的旁路通道,其将大部分流体运送到与杆平行但间隔开的路径上的扩散器区域中。 当提供多个离散旁路通道时,该领是最有效的。

    Method for operating a nuclear reactor with scrammable part length rod
    2.
    发明授权
    Method for operating a nuclear reactor with scrammable part length rod 失效
    用可操作的部件长度杆操作核反应堆的方法

    公开(公告)号:US4169759A

    公开(公告)日:1979-10-02

    申请号:US758126

    申请日:1977-01-10

    申请人: Frank Bevilacqua

    发明人: Frank Bevilacqua

    IPC分类号: G21C7/103 G21C7/08

    摘要: A new part length rod is provided which may be used to not only control xenon induced power oscillations but also to contribute to shutdown reactivity when a rapid shutdown of the reactor is required. The part length rod consists of a control rod with three regions. The lower control region is a longer weaker active portion separated from an upper stronger shorter poison section by an intermediate section which is a relative non-absorber of neutrons. The combination of the longer weaker control section with the upper high worth poison section permits the part length rod of this invention to be scrammed into the core. When a reactor shutdown is required but also permits the control rod to be used as a tool to control power distribution in both the axial and radial directions during normal operation.

    摘要翻译: 提供了新的部分长度杆,其可以用于不仅控制氙感应功率振荡,而且还需要在需要快速关闭反应器时有助于关闭反应性。 部件长度杆由具有三个区域的控制杆组成。 较低的控制区域是较长的较弱的有效部分,通过作为中子的相对非吸收体的中间部分与较强的较短的中毒部分分离。 较长的较弱的控制部分与上部高价值毒物部分的组合允许将本发明的部分长度杆切割成芯部。 当需要停堆时,也允许控制杆用作在正常操作期间在轴向和径向方向上控制功率分配的工具。

    Fissionable mass storage device
    4.
    发明授权
    Fissionable mass storage device 失效
    可裂解大容量存储设备

    公开(公告)号:US4044267A

    公开(公告)日:1977-08-23

    申请号:US671182

    申请日:1976-03-26

    申请人: Frank Bevilacqua

    发明人: Frank Bevilacqua

    CPC分类号: G21C19/40 G21F5/012

    摘要: An apparatus for the safe storage of a plurality of fissionable masses including an array of discrete neutron absorbing shields which utilizes the principle of the neutron trap to reduce the multipication factor of the storage array to a subcritical value when immersed in a neutron moderating medium. Each discrete neutron absorbing shield is designed to perimetrically encircle each of the stored fissionable masses. Each shield is spaced such that the encircled fissionable mass is spaced from the next adjacent neutron absorbing shield by a distance determined by the enrichment of the fissionable masses and attenuation of the moderating medium.

    摘要翻译: 一种用于安全存储多个可裂变质量的装置,包括分立的中子吸收屏蔽阵列,其利用中子阱的原理将其浸入中子调节介质中时将储存阵列的多重因子降低到亚临界值。 每个离散的中子吸收屏蔽被设计成围绕每个储存的可裂变质量块。 每个屏蔽间隔开,使得环绕的可裂变质量与下一个相邻的中子吸收屏蔽隔开距离,该距离由可裂变质量的浓缩和调节介质的衰减确定。

    Passive residual heat removal system for nuclear power plant
    5.
    发明授权
    Passive residual heat removal system for nuclear power plant 失效
    核电厂被动残余除热系统

    公开(公告)号:US4239596A

    公开(公告)日:1980-12-16

    申请号:US861229

    申请日:1977-12-16

    IPC分类号: G21C15/18

    CPC分类号: G21C15/18 Y02E30/40

    摘要: An enclosed reservoir is sized and located in relation to the steam generator of a pressurized water nuclear reactor power plant so that upon a loss of feedwater flow to the steam generator, a gravity induced supplementary flow into the steam generator is automatically initiated to dissipate the residual heat generated in the reactor. The height of the reservoir is the same as the distance between upper and lower design limits on steam generator feedwater level. The top of the steam generator is fluidly connected to the top of the reservoir to equalize the pressure therebetween. The gravity induced flow from the reservoir to the steam generator produces a water level in the steam generator that stays within the upper and lower design limits.

    摘要翻译: 封闭的储存器的尺寸和位置相对于加压水核反应堆发电厂的蒸汽发生器定位,使得在给予蒸汽发生器的给水流量的损失时,自动启动重力引入到蒸汽发生器中的辅助流,以消除残余物 在反应堆中产生的热量。 储水器的高度与蒸汽发生器给水量上限和下限之间的距离相同。 蒸汽发生器的顶部流体地连接到储存器的顶部以均衡其间的压力。 重力引起的从储存器到蒸汽发生器的流动产生的蒸汽发生器中的水位保持在上限和下限设计范围内。

    Nuclear fuel storage
    6.
    发明授权
    Nuclear fuel storage 失效
    核燃料储存

    公开(公告)号:US4177385A

    公开(公告)日:1979-12-04

    申请号:US834634

    申请日:1977-09-19

    申请人: Frank Bevilacqua

    发明人: Frank Bevilacqua

    CPC分类号: G21C19/40 G21C3/34 Y02E30/40

    摘要: A method and apparatus for the storage of fuel in a stainless steel egg crate structure within a storage pool. Fuel is initially stored in a checkerboard pattern or in each opening if the fuel is of low enrichment. Additional fuel (or fuel of higher enrichment) is later stored by adding stainless steel angled plates within each opening, thereby forming flux traps between the openings. Still higher enrichment fuel is later stored by adding poison plates either with or without the stainless steel angles.

    摘要翻译: 一种用于在储存池内的不锈钢蛋箱结构中储存燃料的方法和装置。 如果燃料浓度低,则燃料最初存储在棋盘图案或每个开口中。 通过在每个开口内加入不锈钢角板,随后储存额外的燃料(或更高浓度的燃料),从而在开口之间形成通量阱。 更高的富集燃料后来通过添加有或没有不锈钢角度的毒药来储存。

    Nuclear reactor with scrammable part length rod
    7.
    发明授权
    Nuclear reactor with scrammable part length rod 失效
    核反应堆具有可加工的部分长度的棒

    公开(公告)号:US4169760A

    公开(公告)日:1979-10-02

    申请号:US758125

    申请日:1977-01-10

    申请人: Frank Bevilacqua

    发明人: Frank Bevilacqua

    IPC分类号: G21C7/103 G21C7/08

    摘要: A new part length rod is provided which may be used to not only control xenon induced power oscillations but also to contribute to shutdown reactivity when a rapid shutdown of the reactor is required. The part length rod consists of a control rod with three regions. The lower control region is a longer weaker active portion separated from an upper stronger shorter poison section by an intermediate section which is a relative non-absorber of neutrons. The combination of the longer weaker control section with the upper high worth poison section permits the part length rod of this invention to be scrammed into the core. When a reactor shutdown is required but also permits the control rod to be used as a tool to control power distribution in both the axial and radial directions during normal operation.

    摘要翻译: 提供了新的部分长度杆,其可以用于不仅控制氙感应功率振荡,而且还需要在需要快速关闭反应器时有助于关闭反应性。 部件长度杆由具有三个区域的控制杆组成。 较低的控制区域是较长的较弱的有效部分,通过作为中子的相对非吸收体的中间部分与较强的较短的中毒部分分离。 较长的较弱的控制部分与上部高价值毒物部分的组合允许将本发明的部分长度杆切割成芯部。 当需要停堆时,也允许控制杆用作在正常操作期间在轴向和径向方向上控制功率分配的工具。

    Spent fuel storage improvement
    8.
    发明授权
    Spent fuel storage improvement 失效
    乏燃料储存改善

    公开(公告)号:US4024406A

    公开(公告)日:1977-05-17

    申请号:US658649

    申请日:1976-02-17

    申请人: Frank Bevilacqua

    发明人: Frank Bevilacqua

    CPC分类号: G21C19/40

    摘要: An apparatus for the safe storage of a plurality of fissionable masses including an array of discrete neutron absorbing shields which utilizes the principle of the neutron trap to reduce the multiplication factor of the storage array to a subcritical value when immersed in a neutron moderating medium. Each discrete neutron absorbing shield is spaced such that the encircled fissionable mass is spaced from the next adjacent neutron absorbing shield by a distance determined by the enrichment of the fissonable masses and attenuation of the moderating medium.

    摘要翻译: 一种用于安全存储多个可裂变质量的装置,包括分立的中子吸收屏蔽阵列,其利用中子阱的原理将其沉积在中子调节介质中时将存储阵列的倍增因子减小到亚临界值。 每个离散的中子吸收屏蔽物间隔开,使得环绕的可裂变质量与下一个相邻的中子吸收屏蔽隔开一定距离,该距离由可裂解质量的浓缩和调节介质的衰减确定。

    Method and apparatus for a nuclear reactor for increasing reliability to
scram control elements
    9.
    发明授权
    Method and apparatus for a nuclear reactor for increasing reliability to scram control elements 失效
    用于提高可控性的核反应堆的方法和装置

    公开(公告)号:US3959071A

    公开(公告)日:1976-05-25

    申请号:US473606

    申请日:1974-05-28

    申请人: Frank Bevilacqua

    发明人: Frank Bevilacqua

    摘要: A method and apparatus for increasing the reliability of linear drive devices of a nuclear reactor to scram the control elements held in a raised position thereby. Each of the plurality of linear drive devices includes a first type of holding means associated with the drive means of the linear drive device and a second type of holding means distinct and operatively dissimilar from the first type. The system of linear drive devices having both types of holding means are operated in such a manner that the control elements of a portion of the linear drive devices are only held in a raised position by the first holding means and the control elements of the remaining portion of linear drive devices are held in a raised position by only the second type of holding means. Since the two types of holding means are distinct from one another and are operatively dissimilar, the probability of failure of both systems to scram as a result of common mode failure will be minimized. Means may be provided to positively detect disengagement of the first type of holding means and engagement of the second type of holding means for those linear drive devices being operative to hold the control elements in a raised position with the second type of holding means.

    摘要翻译: 一种用于提高核反应堆的线性驱动装置的可靠性的方法和装置,以便将由此保持在升高位置的控制元件排除。 多个线性驱动装置中的每一个包括与线性驱动装置的驱动装置相关联的第一类型的保持装置和与第一类型不同且可操作地不同的第二类型的保持装置。 具有两种类型的保持装置的线性驱动装置的系统以这样的方式操作,使得直线驱动装置的一部分的控制元件仅由第一保持装置和剩余部分的控制元件保持在升高位置 的线性驱动装置仅通过第二类型的保持装置保持在升高位置。 由于两种类型的保持装置彼此不同并且是可操作地不同的,所以两个系统由于共模故障导致的故障的可能性将被最小化。 可以提供装置来主动地检测第一类型的保持装置的脱离和用于那些线性驱动装置的第二类型的保持装置的接合,其可操作以将控制元件保持在与第二类型的保持装置的升高位置中。

    Heated junction thermocouple level measurement apparatus

    公开(公告)号:US4440717A

    公开(公告)日:1984-04-03

    申请号:US298436

    申请日:1981-09-01

    摘要: A liquid level sensing apparatus (32) senses the level of liquid surrounding the apparatus. A plurality of axially spaced sensors (36) are enclosed in a separator tube (86). The separator tube (86) tends to collapse the level of a two-phase fluid within the separator tube into essentially a liquid phase and a gaseous phase where the collapsed level bears a relationship to the coolant inventory outside the separator tube. The level of the liquid phase is sensed by level sensing apparatus (32). The separator tube (86) contains inlet-outlet ports (90,92) near the top and bottom thereof to equalize the liquid level inside and outside the separator tube (86) when the level fluctuates or the water within the separator tube (86) flashes to steam. Each sensor (36) is comprised of a heater (64), a heated thermocouple junction (68) and an unheated thermocouple junction (66) within an elongated heat conductive housing (62). The heated portion of housing (62) is enclosed in a splash guard (72) with inlet-outlet ports ( 78,82) near the top and bottom to equalize the liquid level inside and outside the splash guard (72) and to eliminate the spurious indications of liquid level change which may arise if water droplets contact the housing (62) in the region of the heater. To prevent steam bubbles entrained in a two-phase fluid cross flow from entering the lateral inlet-outlet ports (90,92) of the separator tube (86), the separator tube (86) is enclosed in support tube (100) which may in turn be enclosed in an otherwise unused control element assembly shroud (110). The lateral inlet-outlet ports (90,92) of separator tube (86) are axially offset from lateral inlet-outlet ports (102) of support tube 100 at least where support tube 100 is subjected to cross flow. The shroud (110) is open on the bottom and has lateral inlet-outlet ports (112) to facilitate liquid level fluctuations to equalize inside and outside shroud (110). An alternate embodiment permits the measurement of more than one liquid level.