Feedwater control system considering pressure drop of feedwater control valve in nuclear power plant and control method therefor
    81.
    发明申请
    Feedwater control system considering pressure drop of feedwater control valve in nuclear power plant and control method therefor 有权
    考虑核电厂给水控制阀压降的给水控制系统及其控制方法

    公开(公告)号:US20050072380A1

    公开(公告)日:2005-04-07

    申请号:US10885681

    申请日:2004-07-08

    IPC分类号: G21D3/08 G21D3/14 G21C7/36

    摘要: A feedwater control system considering a pressure drop of feedwater control valve in a nuclear power plant and a control method therefor are provided. In the feedwater control system, a first detection unit includes: a flow error signal generator for generating a flow error signal corresponding to a difference between a steam flow signal and a feedwater flow signal; and a water level correction error signal generator for generating a water level correction error signal corresponding to a sum of a water level measurement signal and the flow error signal. A second detection unit includes: a pressure drop sensor unit for detecting a pressure difference between front and rear portions of at least one feedwater control valve among the main feedwater control valves and the downcorner feedwater control valves and generating a pressure drop signal corresponding to the detected pressure difference; a pressure drop setup value signal generator for generating a pressure drop setup value signal corresponding to a previously set pressure drop setup value of the feedwater control valves; and a pressure drop error signal generator for comparing the pressure drop signal with the pressure drop setup value signal and generating a pressure drop error signal. A control unit controls the main feedwater pump based on a correction control signal output from the correction control signal generator.

    摘要翻译: 提供考虑核电站给水控制阀压降的给水控制系统及其控制方法。 在给水控制系统中,第一检测单元包括:流量误差信号发生器,用于产生对应于蒸汽流量信号和给水流量信号之间的差的流量误差信号; 以及水位校正误差信号发生器,用于产生对应于水位测量信号和流量误差信号之和的水位校正误差信号。 第二检测单元包括:压降传感器单元,用于检测主给水控制阀和下压给水控制阀中的至少一个给水控制阀的前后部分之间的压力差,并产生与检测到的压降信号相对应的压降信号 压力差 压降设定值信号发生器,用于产生与预定设定的给水控制阀的压降设定值对应的压降设定值信号; 以及压降误差信号发生器,用于将压降信号与压降建立值信号进行比较并产生压降误差信号。 控制单元基于从校正控制信号发生器输出的校正控制信号来控制主给水泵。

    Method for generating control system setpoints with implicit dependencies
    82.
    发明授权
    Method for generating control system setpoints with implicit dependencies 失效
    用隐式依赖产生控制系统设定值的方法

    公开(公告)号:US5953238A

    公开(公告)日:1999-09-14

    申请号:US614023

    申请日:1996-03-12

    CPC分类号: G05B17/02

    摘要: A method for modeling linear control systems that are asymptotically stable provided that any initial deviation is within a definite bound is described. The method includes the steps of generating a parametric model of the quasi steady state system, generating a time-invariant parametric mapping function, using the system model, to relate a system setpoint parameter at a system setpoint function to an input process parameter implicit in a system implicit parameter, and generating an interface protocol to adjust the time-invariant parametric mapping function to account for any time-dependent variations in the relative performance between the input process parameter and the implicit system parameter.

    摘要翻译: 描述渐近稳定的线性控制系统建模方法,只要任何初始偏差在一定范围内即可。 该方法包括以下步骤:产生准稳态系统的参数模型,使用系统模型产生时不变参数映射函数,以将系统设定点功能处的系统设定点参数与隐含在系统设定点功能中的输入过程参数相关联 系统隐式参数,以及生成接口协议来调整时变参数映射函数,以考虑输入过程参数和隐式系统参数之间的相对性能的任何时间相关变化。

    Radiation-induced palladium doping of metals to protect against stress
corrosion cracking
    83.
    发明授权
    Radiation-induced palladium doping of metals to protect against stress corrosion cracking 失效
    金属的辐射诱导钯掺杂,以防止应力腐蚀开裂

    公开(公告)号:US5602888A

    公开(公告)日:1997-02-11

    申请号:US416656

    申请日:1995-04-05

    摘要: A method for mitigating crack growth on the surface of stainless steel or other alloy components in a water-cooled nuclear reactor wherein a solution or suspension of a compound containing a noble metal is injected into the coolant water while the reactor is not generating nuclear heat, e.g., during shutdown or recirculation pump heatup. During shutdown, the reactor coolant water reaches temperatures as low as 120.degree. F., in contrast to the water temperature of 550.degree. F. during normal operation. During pump heatup, the water temperature reaches 400.degree.-450.degree. F. At these reduced temperatures, the rate of thermal decomposition of the injected noble metal compound is reduced. However, radiation-induced decomposition also occurs inside the reactor. In particular, the noble metal compound can be decomposed by the gamma radiation emanating from the nuclear fuel core of the reactor. The noble metal compound decomposes under reactor thermal and radiation conditions to release ions/atoms of the noble metal which incorporate in or deposit on the oxide film formed on the stainless steel and other alloy components. As a result, the electrochemical potential of the metal surface is maintained at a level below the critical potential in the presence of low levels of hydrogen to protect against intergranular stress corrosion cracking.

    摘要翻译: 一种用于减轻水冷核反应堆中不锈钢或其他合金组分表面上的裂纹扩展的方法,其中将含有贵金属的化合物的溶液或悬浮液注入冷却水中,同时反应器不产生核热, 例如在停机或再循环泵加热期间。 在停机期间,反应堆冷却水的温度低至120°F,与正常运行时的550°F水温相反。 在泵加热期间,水温达到400°-450°F。在这些降低的温度下,注入的贵金属化合物的热分解速率降低。 然而,辐射诱导的分解也发生在反应器内部。 特别地,贵金属化合物可以通过从反应器的核燃料芯发出的γ射线分解。 贵金属化合物在反应器热和辐射条件下分解,以释放掺入或沉积在不锈钢和其它合金组分上形成的氧化膜上的贵金属的离子/原子。 因此,在低水平的氢气存在下,金属表面的电化学势能保持在低于临界电位的水平,以防止晶间应力腐蚀开裂。

    Method for treating the primary cooling medium of a pressurized water
nuclear reactor
    86.
    发明授权
    Method for treating the primary cooling medium of a pressurized water nuclear reactor 失效
    用于处理加压水核反应堆的初级冷却介质的方法

    公开(公告)号:US5315626A

    公开(公告)日:1994-05-24

    申请号:US926579

    申请日:1992-08-06

    CPC分类号: G21C19/307

    摘要: The invention is of a method for treating the primary cooling medium of a pressurized water nuclear reactor by controlling its efficiency through the H.sub.3 BO.sub.3 content in the cooling medium. Hydrazine hydrate (N.sub.2 H.sub.4 .multidot.H.sub.2 O) is continuously fed to the coolant of a reactor which is charged for energy generation, to such an extent that its content equals 5.10.sup.-6 to 5.10.sup.-2 g/kg coolant medium as well as KOH and/or LiOH which corresponds to the alkaline properties. KOH in an amount of 80 to 56 mg/kg cooling medium with respect to the amount of H.sub.3 BO.sub.3 in a range of 20 to 0 g/kg cooling medium and the excess hydrogen is removed from the system leaving a maximum amount of hydrogen in the coolant medium of 100 n.multidot.ml/kg.

    摘要翻译: 本发明是通过控制其在冷却介质中的H3BO3含量的效率来处理加压水核反应堆的主要冷却介质的方法。 将水合肼(N 2 H 4 xH 2 O)连续供给到用于产生能量的反应器的冷却剂中,使其含量等于5.10-6至5.10-2g / kg冷却剂介质以及KOH和/或LiOH, 对应于碱性。 KOH的量为80至56mg / kg冷却介质,相对于在20至0g / kg冷却介质的范围内的H3BO 3的量,并且从体系中除去过量的氢气,在冷却剂中留下最大量的氢气 培养基为100 nxml / kg。

    Boiling water nuclear reactor and start-up process thereof
    87.
    发明授权
    Boiling water nuclear reactor and start-up process thereof 失效
    沸水核反应堆及其启动过程

    公开(公告)号:US5271044A

    公开(公告)日:1993-12-14

    申请号:US851198

    申请日:1991-03-14

    IPC分类号: G21D3/08 G21C7/00

    摘要: In a boiling water nuclear reactor, a reactor primary cooling water line is filled with water at the start-up time, and the inside of a pressure vessel is pressurized by a pressurized tank and at the same time control rods are withdrawn to thereby heat cooling water in a state of single-phase flow to high temperature. Succeedingly, the pressurization is released and the pressure of the pressure vessel is gradually approximated to the saturation pressure corresponding to the cooling water temperature to thereby make the cooling water transit into a state of two-phase flow, and thereafter the cooling water is heated by nuclear reaction in the state of two-phase flow to thereby obtain predetermined reactor running temperature and pressure. This prevents the flow fluctuation and the reduction of stability of core due to occurrence of unstable phenomena of low temperature two-phase flow at the start-up time of the reactor to thereby make it possible to perform stable starting-up of the reactor and to shorten the start-up time of the reactor to thereby realize improvement in economy as well as reliability.

    摘要翻译: 在沸水核反应堆中,反应器一次冷却水管线在启动时由水填充,压力容器的内部由加压罐加压,同时将控制棒取出,从而加热冷却 水处于单相流向高温状态。 成功地释放加压,压力容器的压力逐渐接近对应于冷却水温度的饱和压力,从而使冷却水进入两相流动状态,之后将冷却水加热 核反应处于两相流状态,从而获得预定的反应器运行温度和压力。 由此,由于在反应器的起动时由于低温两相流的不稳定现象的发生而防止了芯的流动波动和稳定性的降低,从而能够稳定地起动反应器, 缩短反应堆的启动时间,从而实现经济性和可靠性的提高。

    Process and device for removing flammable gas mixtures in a gas space
    88.
    发明授权
    Process and device for removing flammable gas mixtures in a gas space 失效
    在气体空间中去除易燃气体混合物的方法和装置

    公开(公告)号:US5230859A

    公开(公告)日:1993-07-27

    申请号:US613883

    申请日:1990-12-14

    申请人: Johannes Wiesemes

    发明人: Johannes Wiesemes

    CPC分类号: G21C9/00 G21C19/317 Y02E30/40

    摘要: To ensure safe removal of flammable explosive gaseous mixtures, the flammable mixtures are burned and/or recombined in partial volumes of the container separated from the rest of the container by metal grilles (18,19). The combustion is thereby prevented from spreading by the principle of the Davy safety lamp. The combustion and/or recombination in the partial volumes is effected by means of ignition sources (20), such as electric sparks, hot surfaces, open flames and/or catalytic surfaces. The heat energy released during combustion is transferred by means of cooling devices such as heat pipes. The temperature of the grille is sued to control the energy supply of the ignition source(s) and should never exceed approximately 2/3 of the ignition temperature of the flammable gaseous mixture; when the temperature reaches 3/4 of the ignition temperature, a fuse cuts off the energy supply. If the grille suffers mechanical damage, it touches an electrically insulated internal grille. This spark-free contact triggers an electrical switch which cuts off the power supply to the ignition and/or glow plugs. Detonatable H2-air mixtures can thereby be removed without the risk of explosion.

    摘要翻译: PCT No.PCT / DE89 / 00383 Sec。 371 1990年12月14日第 102(e)1990年12月14日的PCT PCT 1989年6月13日PCT公布。 第WO89 / 12897号公报 日期为1989年12月28日。为了确保易燃易爆气体混合物的安全清除,易燃混合物通过金属格栅(18,19)与部分容器的部分体积燃烧和/或重组。 因此,通过Davy安全灯的原理防止燃烧蔓延。 部分体积中的燃烧和/或重组通过点火源(20)进行,例如电火花,热表面,明火和/或催化表面。 燃烧过程中释放的热能通过热管等冷却装置传递。 控制格栅的温度来控制点火源的能量供应,不应超过易燃气体混合物的点火温度的2/3左右; 当温度达到点火温度的3/4时,保险丝会切断能量供应。 如果格栅受到机械损坏,则会接触电绝缘的内部格栅。 该无火花触点触发电气开关,切断点火和/或电热塞的电源。 因此可以除去可爆炸的H 2空气混合物,而不会有爆炸的危险。

    Sensor for controlling water quality of reactor and method of
controlling said water chemistry
    90.
    发明授权
    Sensor for controlling water quality of reactor and method of controlling said water chemistry 失效
    用于控制反应器水质的传感器和控制水化学物质的方法

    公开(公告)号:US5201229A

    公开(公告)日:1993-04-13

    申请号:US603328

    申请日:1990-10-25

    申请人: Hidefumi Ibe

    发明人: Hidefumi Ibe

    CPC分类号: G01N27/12 G01N27/205

    摘要: An element (e.g., a sensor) has a fine-line thin film of a conductor formed on a non-conductive substrate, and a change of physical properties (e.g., deformation) of the substrate or the ambient environment is detected through a change in physical properties of the conductor. The element is manufactured by forming a layered film, composed of a semiconductor and a conductor, on the substrate, and forcibly diffusing part of this film, e.g., by selective irradiation with high-energy ions, to form this part into an alloy semi-conductor, thereby providing a two-dimensional pattern of the fine lines of the conductor and the semiconductor. By arranging a plurality of fine lines of a conductor transversely to a direction of growth of a crack in the substrate, crack in the substrate is detected through a change in electrical resistance of the fine lines. A dissolved oxygen sensor, a hydrogen sensor, and an electrical conductivity sensor (of an ambient medium) can also be provided. To control water chemistry of a reactor, an amount of a water chemistry improving agent injected is controlled in accordance with an output of a water chemistry measurement sensor provided in water in a pressure vessel of the reactor. One or more of a dissolved oxygen sensor, a hydrogen sensor and an electrical conductivity sensor are formed directly on a surface of a structural material of the reactor.