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41. 发明授权

US4748814A Electric power generating plant 失效
标题翻译：发电厂
公开(公告)号：US4748814A
公开(公告)日：1988-06-07
申请号：US876769
申请日：1986-06-20
申请人： Junichi Tanji , Mitsuo Kinoshita
发明人： Junichi Tanji , Mitsuo Kinoshita
IPC分类号： G05D13/62 , F01K3/18 , F01K13/02 , F22B35/00 , G05B11/32 , G21D3/12 , F01K11/00
CPC分类号： G21D3/12 , F01K13/02 , F01K3/181 , Y02E30/40
摘要： A control apparatus for electric power plant comprises turbine speed control means for detecting the speed of a turbine coupled to an electric generator to control the turbine speed by controlling a steam flow supplied to the turbine on the basis of the detected speed, pressure control means for controlling the pressure in a steam generator on the basis of the pressure of the steam generator, and correcting means for correcting the steam flow supplied to the turbine only when fluctuation in the pressure of the steam generator brought about by rapid change of a set load value is deviated from a predetermined range in which the steam pressure is allowed to vary, the correction of the steam flow being made in correspondence to the deviation.
摘要翻译：一种用于电力设备的控制装置，包括涡轮速度控制装置，用于通过根据检测的速度控制供应到涡轮的蒸汽流来检测与发电机相连的涡轮机的速度，以控制涡轮转速，压力控制装置基于蒸汽发生器的压力来控制蒸汽发生器中的压力;以及校正装置，用于仅在设定的负载值的快速变化引起的蒸汽发生器的压力波动时，校正供应到涡轮机的蒸汽流量偏离允许蒸汽压力变化的预定范围，根据该偏差对蒸汽流进行校正。

42. 发明授权

US4240874A Process for controlling the reactivity effects due to the power variations in PWR nuclear reactors 失效
标题翻译：控制由于PWR核反应堆功率变化引起的反应性影响的方法
公开(公告)号：US4240874A
公开(公告)日：1980-12-23
申请号：US917401
申请日：1978-06-20
申请人： Jean-Paul Millot
发明人： Jean-Paul Millot
IPC分类号： G21C7/00 , G21C7/06 , G21C7/22 , G21D3/12 , G21D3/16
CPC分类号： G21D3/16 , G21C7/06 , Y02E30/32 , Y02E30/39
摘要： A process for controlling the reactivity effects due to the power variations in a nuclear reactor using pressurized water comprises moving movable clusters of absorbent material inside the fuel units of the reactor, the clusters comprising first sets of which at least one has an anti-reactivity of less than 700 ppht, and a second set which is composed of very absorbent clusters, the first sets being moved solely as a function of the power required of the turbine to vary the power of the reactor and the second set being moved simultaneously in dependence on the difference between the actual mean temperatures of the reactor core and a reference temperature which is a function of the level of power required.
摘要翻译：用于控制由于使用加压水的核反应堆的功率变化引起的反应性影响的方法包括在反应器的燃料单元内移动可移动的吸收材料簇，所述簇包含第一组至少一种具有抗反应性小于700 ppht，第二组由非常吸收性的群组组成，第一组仅作为涡轮机所需功率的函数而移动，以改变反应器的功率，而第二组根据反应堆堆芯的实际平均温度与作为所需功率水平的函数的参考温度之间的差异。

43. 发明授权

US4187144A Nuclear reactor power supply 失效
标题翻译：核反应堆电源
公开(公告)号：US4187144A
公开(公告)日：1980-02-05
申请号：US799632
申请日：1977-05-23
申请人： Norman P. Mueller , Boris A. Mutafelija
发明人： Norman P. Mueller , Boris A. Mutafelija
IPC分类号： G21C7/00 , G21C7/22 , G21D3/12 , G21C15/00
CPC分类号： G21D3/12 , Y02E30/40
摘要： The neutron absorbing medium in a reactor is changed in dependence upon the loading of the reactor, or any other operating mode where the power distribution axially is to be maintained within acceptable limits, by varying the chemical shim in the coolant of the reactor. The error for effecting the change is derived by comparing the average temperature of the coolant and a reference temperature which is a programmed function of the power delivered by the turbine energized by the reactor. The reference temperature is derived by converting the turbine impulse chamber pressure into a temperature parameter. A compensated temperature error is derived from an electrical compensating network typically a PID controller. At the input of this network an electrical analog of the temperature error is impressed and its output, a compensated temperature error, is derived. The correcting command is derived from the output of a non-linear gain network. At the input of this gain network the compensated temperature error is impressed. The output is supplied to a facility for changing the neutron-absorbing medium which is connected to the reactor. The compensating network and the gain network may be part of an analog logic system or part of a digital computer system.
摘要翻译：反应器中的中子吸收介质根据反应器的负载或通过改变反应器的冷却剂中的化学垫片将功率分布轴向保持在可接受的限度内的任何其它操作模式而改变。通过比较冷却剂的平均温度和参考温度来得出影响变化的误差，参考温度是由反应堆激励的涡轮机传递的功率的编程功能。通过将涡轮脉冲室压力转换成温度参数来导出参考温度。补偿温度误差来自电气补偿网络，通常是PID控制器。在该网络的输入端，印制温度误差的电气模拟量，并导出其输出，补偿温度误差。校正命令是从非线性增益网络的输出导出的。在这个增益网络的输入端，补偿温度误差是印象深刻的。输出被提供给用于改变连接到反应器的中子吸收介质的设备。补偿网络和增益网络可以是模拟逻辑系统或数字计算机系统的一部分的一部分。

44. 发明授权

US3503205A Gas turbine power plant 失效
公开(公告)号：US3503205A
公开(公告)日：1970-03-31
申请号：US3503205D
申请日：1968-07-29
申请人： SULZER AG
发明人： SUTER PETER
IPC分类号： F02C1/10 , F02C9/18 , G21D3/12 , G21D5/06 , F01K25/00 , F01K3/18
CPC分类号： G21D5/06 , F02C1/10 , F02C9/18 , G21D3/12 , Y02E30/40

45. 发明授权

US3180802A Boiling water nuclear reactor system 失效
标题翻译：沸水核反应堆系统
公开(公告)号：US3180802A
公开(公告)日：1965-04-27
申请号：US7718560
申请日：1960-12-20
申请人： COMBUSTION ENG
发明人： WEST JOHN M , WEEMS STERLING J
IPC分类号： G21C1/08 , G21D3/12 , G21D5/06 , G21D5/08
CPC分类号： G21D3/12 , G21C1/08 , G21D5/06 , G21D5/08 , Y02E30/40

46. 发明授权

US3042600A Reactor control 失效
标题翻译：电抗器控制
公开(公告)号：US3042600A
公开(公告)日：1962-07-03
申请号：US62493156
申请日：1956-11-28
申请人： GEN ELECTRIC
发明人： BROOKS ROBERT D
IPC分类号： G21C1/08 , G21C3/14 , G21C7/26 , G21D3/12
CPC分类号： G21C1/08 , G21C3/14 , G21C7/26 , G21D3/12 , Y02E30/39

47. 发明授权

US5268939A Control system and method for a nuclear reactor 失效
标题翻译：核反应堆的控制系统和方法
公开(公告)号：US5268939A
公开(公告)日：1993-12-07
申请号：US963187
申请日：1992-10-19
申请人： Calvin K. Tang , Wayne Marquino
发明人： Calvin K. Tang , Wayne Marquino
IPC分类号： G21D3/04 , F01K3/18 , F01K9/04 , G21D3/06 , G21D3/12 , G21C7/00
CPC分类号： G21D3/06 , F01K3/181 , F01K9/04 , G21Y2002/201 , G21Y2002/207 , G21Y2004/30 , G21Y2004/401 , Y02E30/40
摘要： A nuclear reactor is joined to a steam turbine by a main steamline for discharging steam thereto. A plurality of flow control valves regulate flow to the turbine, and a bypass valve selectively bypasses a portion of the steam around the turbine to its condenser. A pressure regulator and turbine controller are operatively joined to the control valves and the bypass valve for controlling steamflow to the turbine. An apparatus for detecting failure of one of the control valves is operatively connected to the bypass valve, and upon failure of one of the control valves to channel sufficient flowrate, the bypass valve is automatically opened to reduce reactor pressure rise. The failure detecting apparatus also provides a reduction demand signal for reducing reactor power for allowing the bypass valve to close.

48. 发明授权

US5039473A Method of determining and evaluating the power return capacity of a pressurized water nuclear reactor 失效
标题翻译：确定和评估加压水核反应堆功率回收能力的方法
公开(公告)号：US5039473A
公开(公告)日：1991-08-13
申请号：US333661
申请日：1989-04-05
申请人： Patrick Girieud
发明人： Patrick Girieud
IPC分类号： G21C17/00 , G21C7/36 , G21D3/12 , G21D3/16
CPC分类号： G21C7/36 , G21D3/16 , Y02E30/32 , Y02E30/39
摘要： Method for determining a evaluating the capacity of a pressurized water nuclear reactor to return to power rapidly, consisting in calculating a pick-up power by applying the general formula:Prip=Prel+.DELTA.Pin which Prip is the maximum pick-up power obtainable by acting on the control bars, Prel is the relative power delivered by the core, determined by the in-line measurement of the neutron flow emitted by the core and .DELTA.P is the additional power resulting from the potential reactivity of the assembly of control bars of the reactor when this assembly passes from the observed insertion to the minimum insertion, P being calculated from the measured position of the power regulation clusters, involving the axial power distribution measured (C1 to C6) and the previously defined exhaustion of the core.
摘要翻译：用于确定加压水核反应堆快速返回功率的能力的方法，其包括通过应用以下通式计算拾取功率：Prip = Prel + DELTA P，其中Prip是可由下式获得的最大拾取功率：作用在控制杆上，Prel是由核心发射的中子流的在线测量确定的核心传递的相对功率，DELTA P是由控制棒组件的潜在反应性产生的附加功率当该组件从观察到的插入传递到最小插入时，反应器P从功率调节簇的测量位置计算，涉及所测量的轴向功率分布（C1至C6）和先前确定的芯的耗尽。

49. 发明授权

US4707324A Controlling the response of a pressurized water reactor to rapid fluctuations in load 失效
标题翻译：控制加压水反应堆对负荷的快速波动的响应
公开(公告)号：US4707324A
公开(公告)日：1987-11-17
申请号：US686768
申请日：1984-12-27
申请人： Gary D. Storrick
发明人： Gary D. Storrick
IPC分类号： G21C7/36 , G21D3/12 , G21C7/00
CPC分类号： G21C7/36 , G21D3/12 , Y02E30/32 , Y02E30/39
摘要： The setpoints for control systems in a pressurized water reactor are adjusted by an amount corresponding to the expected change in the controlled process variable resulting from rapid fluctuations in load to reduce the duty time of the control system components such as the rod drive mechanisms in the rod control system and the spray and heater units in the pressurizer pressure control system. In addition, the deadband in the response of the rod control system is continuously varied as a function of the variance of the magnitude of the rapid fluctuations in load to further reduce wear while maintaining good response during load following.
摘要翻译：压力水反应堆中控制系统的设定值被调整为与由负载快速波动引起的受控过程变量的预期变化相对应的量，以减少控制系统部件（例如杆中的杆驱动机构）的占空比控制系统和加压器压力控制系统中的喷雾和加热器单元。另外，杆控制系统的响应中的死区作为负载快速波动幅度变化的函数而不断变化，以进一步减少磨损，同时在负载跟随期间保持良好的响应。

50. 发明授权

US4505873A Method for regulating the power supplied to a steam turbine/pressurized water nuclear reactor 失效
标题翻译：用于调节供应给汽轮机/加压水核反应堆的功率的方法
公开(公告)号：US4505873A
公开(公告)日：1985-03-19
申请号：US235878
申请日：1981-04-03
申请人： Jean-Francois Petetrot , Pierre Parent
发明人： Jean-Francois Petetrot , Pierre Parent
IPC分类号： G21D3/12 , G21C7/36
CPC分类号： G21D3/12 , Y02E30/40
摘要： A method for regulating the power supplied to a steam turbine by a pressurized water nuclear reactor driving an electric current generator supplying a network by utilizing the movement of control rods in the reactor and the by-passing of a fraction of the steam produced by the reactor out from the turbine circuit. In the case of electrical uncoupling between the generator and the network or load rejection, the parameter determining the position of the control rods is selected as the greater of two values of a reference temperature. The by-passing of the steam is kept in operation and the operation of the reactor remains automatic. The opening signal for the by-pass valves is modified by a gain signal determined from a signal representing the power level. The invention is particularly applicable to the regulation of the power of pressurized water nuclear power stations.
摘要翻译：一种用于通过利用反应器中的控制棒的运动和由反应器产生的蒸汽的一部分旁路来调节由加压水核反应堆驱动提供网络的电流发生器供应给蒸汽轮机的功率的方法从涡轮机电路出来。在发电机和网络之间的电解耦或负载抑制的情况下，选择控制棒的位置的参数作为参考温度的两个值中的较大值。蒸汽的旁路保持运行，反应堆的运行保持自动。旁通阀的打开信号由从表示功率水平的信号确定的增益信号修改。本发明特别适用于加压水核电站的功率调节。

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