| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 41 | Automatic steam generator control at low power | US181513 | 1988-04-14 | US4912732A | 1990-03-27 | Gurdip Singh |
| The steam generator water level, the feed water temperature, and the reactor power are continuously measured and a level signal (76), a temperature signal (78), and a power signal (80) commensurate with these measurements are respectively generated. From the power signal and the temperature signal, a target flow signal (84) is generated corresponding to the feedwater flow rate that would produce a stable steam generator water level at the steady state condition of the power signal and the temperature signal. The level signal is compared to a level signal setpoint (54) and a resulting level error signal (86) is generated. The level error signal is adjusted by a gain factor (88) that is dependent on the temperature signal to produce an adjusted level error signal (90). The feedwater flow through the bypass valve is then controlled in response to the target flow signal (84') and the adjusted level error signal. In a preferred implementation of the invention, the transition between low power control using the bypass valve and high power control using the main feed water valve is accomplished by generating a main valve position signal (118), and generating an enable signal (124) when the power signal is within a desired transition power range. When the power is in the transition range, the feedwater flow through the bypass valve is ramped down or up in response to the target flow signal, the adjusted level error signal, and the main valve position signal, as the main feedwater flow increases or decreases. | ||||||
| 42 | Automatic steam generator feedwater control over full power range | US879893 | 1986-06-30 | US4777009A | 1988-10-11 | Gurdip Singh; Charles T. French |
| A water level control for a steam generator of a pressurized water type of nuclear steam supply system varies the water level demand as a function of power. The control also varies the water feed rate after a reactor trip initially as a function of reactor coolant average temperature. | ||||||
| 43 | Model steam generator having an improved feedwater system | US876036 | 1986-06-19 | US4727826A | 1988-03-01 | Robert Draper; Donald G. Lorentz |
| A model steam generator including an improved feedwater system for monitoring the conditions of the heat exchange tubes within a nuclear steam generator is disclosed herein. The feedwater system generally comprises a first conduit fluidly connected between the boiler vessel of the model steam generator and the feedwater of the nuclear steam generator via a first valve, and a second conduit which is fluidly connected between this boiler vessel and a feedwater reservoir by way of a second valve. The feedwater reservoir is in turn connected to a source of demineralized, deaerated water by means of a third conduit having a third valve. This reservoir is further fluidly connected to the feedwater of the nuclear steam generator by means of a fourth conduit having a fourth valve. The improved feedwater system of the invention gives the operator three running options. First, he may run the model steam generator directly off the feedwater used in the nuclear steam generator. Second, he may fill the reservoir with feedwater used in the nuclear steam generator and mix anti-corrosive or cleaning additives into this feedwater before introducing it into the model steam generator in order to test their efficacy. Finally, if anti-corrosive or cleaning additives are already in use in the nuclear steam generator, he may fill the reservoir with demineralized, deaerated water and test alternative additives. The improved feedwater system also includes a means for maintaining a turbulent flow through the feedwater inlet conduit so that particulate contaminants in the feedwater will not have an opportunity to settle out before the feedwater is introduced into the model steam generator. | ||||||
| 44 | Model steam generator having a thermosyphon heating means | US636438 | 1984-07-31 | US4660510A | 1987-04-28 | Robert Draper |
| A model steam generator for simulating the environment inside a nuclear steam generator in order to monitor the condition of the heat exchange tubes of the nuclear steam generator is disclosed herein. The model steam generator includes an electrically-powered thermosyphon heating means for circulating a flow of vapor and condensate through the sample tube in a closed loop. The thermosyphon includes riser tubes which are concentrically disposed within the sample heat exchange tube along a substantial portion of the longitudinal axis thereof for both directing a stream of steam into the inside walls of the heat exchange tubes, and for insulating this flow of steam from the resulting stream of condensate which flows down from the inner walls of the sample tubes. The elimination of the counter-current forces between the stream of steam and the downflowing film of condensate prevents the formation of heat-obstructing ripples of condensate on the inner walls of the sample heat exchange tubes. The elimination of these heat-obstructing ripples results in a substantially uniform pattern of heat flux along the longitudinal axis of the sample tube which accurately simulates the pattern of heat flux in the heat exchange tubes of the nuclear steam generator being monitored. | ||||||
| 45 | Model steam generator having an improved feedwater system | US636449 | 1984-07-31 | US4635589A | 1987-01-13 | Robert Draper; Donald G. Lorentz |
| A model steam generator including an improved feedwater system for monitoring the conditions of the heat exchange tubes within a nuclear steam generator is disclosed herein. The feedwater system generally comprises a first conduit fluidly connected between the boiler vessel of the model steam generator and the feedwater of the nuclear steam generator via a first valve, and a second conduit which is fluidly connected between this boiler vessel and a feedwater reservoir by way of a second valve. The feedwater reservoir is in turn connected to a source of demineralized, deaerated water by means of a third conduit having a third valve. This reservoir is further fluidly connected to the feedwater of the nuclear steam generator by means of a fourth conduit having a fourth valve. The improved feedwater system of the invention gives the operator three running options. First, he may run the model steam generator directly off the feedwater used in the nuclear steam generator. Second, he may fill the reservoir with feedwater used in the nuclear steam generator and mix anti-corrosive or cleaning additives into this feedwater before introducing it into the model steam generator in order to test their efficacy. Finally, if anti-corrosive or cleaning additives are already in use in the nuclear steam generator, he may fill the reservoir with demineralized, deaerated water and test alternative additives. The improved feedwater system also includes a means for maintaining a turbulent flow through the feedwater inlet conduit so that particulate contaminants in the feedwater will not have an opportunity to settle out before the feedwater is introduced into the model steam generator. | ||||||
| 46 | Model steam generator having means to facilitate inspection of sample tubes | US636450 | 1984-07-31 | US4628870A | 1986-12-16 | Robert Draper; Donald G. Lorentz |
| A model steam generator including a system for facilitating the inspection of the sample tubes within the boiler vessel of the model generator is disclosed herein. The system includes means for detachably connecting the tubesheet from the primary and secondary sides of the boiler vessel. In the preferred embodiment, both end of the tubesheet and the abutting ends of the primary and secondary sides of the boiler vessel are circumscribed by tapered flanges. The tubesheet is detachably connected from the primary and secondary sides of the boiler vessel by means of Grayloc.RTM.-type annular clamps which are circumscribed by grooves for receiving the abutting flanges at the tubesheet joints. Additionally, the system includes a frame for suspending the secondary side of the boiler vessel, a wheeled cart having a jack for both laterally and vertically moving the primary side of the boiler vessel and the tubesheet into a clamping position onto the secondary side of the boiler vessel. The system further includes a set of threaded guide rods and sleeves for properly aligning the primary side and tubesheet with the secondary side of the generator. The detachably connectable Grayloc.RTM.-type joints between the tubesheet and the primary and secondary sides of the boiler vessel, in combination with the cart and screw jack, afford a convenient means of disassembling the boiler vessel and inspecting the sample heat exchange tubes within the model steam generator. | ||||||
| 47 | Nuclear reactor power supply | US231521 | 1981-02-04 | US4427620A | 1984-01-24 | Bruce M. Cook |
| The redundant signals from the sensor assemblies measuring the process parameters of a nuclear reactor power supply are transmitted each in its turn to a protection system which operates to actuate the protection apparatus for signals indicating off-process conditions. Each sensor assembly includes a number of like sensors measuring the same parameters. The protection system has a number of separate protection units, each unit receiving the process signals from the like sensors of each assembly in its turn. The sets of process signals derived from the sensor parameter assemblies are each in its turn transmitted from the protection system to the control system which impresses control signals on the reactor or its components to counteract the tendency for conditions to drift off-normal status requiring operation of the protection system. A parameter signal selector is interposed between the protection system and the control system. This selector prevents a parameter signal of a set of signals, which differs from the other parameter signals of the set by more than twice the allowable variation of the sensors which produce the set, from passing to the control system. The connection between the protection units and the selector is four separate fiber optic channels so that electrical interaction between the protection units and the selector or control system is precluded. The selectors include a pair of signal selection units, one unit sending selected process signals to primary control channels and the other sending selected process signals to back-up control channels. Test signals are periodically impressed on a selected pair of a selected unit and control channels. When test signals are so impressed the selected control channel is disabled from transmitting control signals to the reactor and/or its associated components. | ||||||
| 48 | Power generation | US239710 | 1981-03-02 | US4424186A | 1984-01-03 | Bruce M. Cook |
| Excessive swing of the feedwater in power supply apparatus on the occurrence of a transient is suppressed by injecting an anticipatory compensating signal into the control for the feedwater. Typical overshoot occurs on removal of a large part of the load, the steam flow is reduced so that the conventional control system reduces the flow of feedwater. At the same time there is a reduction of feedwater level in the steam generator because of the collapse of the bubbles under increased steam pressure. By the time the control responds to the drop in level, the apparatus has begun to stabilize so that there is overshoot. The anticipatory signal is derived from the boiling power which is a function of the nuclear power developed, the enthalpy of saturated water and the enthalpy of the feedwater injected into the steam generator. From the boiling power and the increment in steam pressure resulting from the transient are anticipatory increment of feedwater flow is derived. Thus increment is added to the other parameters controlling the feedwater. | ||||||
| 49 | Method of heating working medium in the heat exchanger of a nuclear reactor installation | US47828365 | 1965-08-09 | US3349003A | 1967-10-24 | JAKOB KAGI |
| 50 | Method of and apparatus for controlling a nuclear reactor vapor generating plant | US39512164 | 1964-09-09 | US3332849A | 1967-07-25 | JAKOB KAGI |
| 51 | Once-through boiler and method of operating the boiler | US4312460 | 1960-07-15 | US3127877A | 1964-04-07 | PAUL PROFOS |
| 52 | Controlled relief system | US71089058 | 1958-01-24 | US3102394A | 1963-09-03 | HARTFIELD GRADY L; WASSEN HENRY A VAN |
| 53 | TOTAL INTEGRATED TUBE ANALYSIS | EP15821763.8 | 2015-07-16 | EP3170184A1 | 2017-05-24 | LE, Qui V.; BEEHNER, Stephen J. |
| The invention relates to improved systems and methods for inspecting the tubes of a steam generator of a nuclear reactor that involves modeling the steam generator, comparing signals of a tube from an eddy current sensor with aspects of the model to determine whether further analysis is required, employing primary and secondary analysis processes, and producing a combined report of the primary and secondary analysis results. | ||||||
| 54 | HIGH-TEMPERATURE GAS REACTOR STEAM GENERATOR SYSTEM | EP12839477 | 2012-10-12 | EP2767981A4 | 2015-06-17 | MINATSUKI ISAO; MIZOKAMI YORIKATA; OYAMA SUNAO; TSUKAMOTO HIROKI |
| A high temperature gas cooled reactor steam generation system (1) includes a nuclear reactor (2) that has helium gas as a primary coolant and heats the primary coolant by heat generated by a nuclear reaction that decelerates neutrons by a graphite block, a steam generator (3) that has water as a secondary coolant and heats the secondary coolant by the primary coolant via the nuclear reactor (2) to generate steam, a steam turbine (4) that is operated by the steam from the steam generator (3), and a generator (5) that generates electricity according to an operation of the steam turbine (4). Moreover, the system (1) includes pressure adjustment means for setting a pressure of the secondary coolant in the steam generator (3) to be lower than a pressure of the primary coolant in the nuclear reactor (2). | ||||||
| 55 | PROCEDE ET DISPOSITIF D'ALIMENTATION D'AU MOINS UN GENERATEUR DE VAPEUR D'UN REACTEUR NUCLAIRE A EAU SOUS PRESSION PENDANT LES PERIODES D'ARRET DU REACTEUR | EP02767567.7 | 2002-07-11 | EP1410401B8 | 2008-10-15 | DAGARD, Philippe |
| At least one injector condenser ( 20 ) is used to supply secondary feedwater to the steam generator ( 1 ) during a phase in the course of which the temperature and the pressure of the coolant of the reactor coolant system ( 2 ) of the nuclear reactor are varied between hot shutdown conditions of the nuclear reactor and conditions making it possible to bring into service the residual heat cooling system (RRA). The injector condenser ( 20 ) is fed with steam withdrawn from an upper part of the steam generator ( 1 ), at a first inlet, and with feedwater from a storage tank ( 10 ), at a second inlet. High-temperature pressurized feedwater is supplied to the steam generator ( 1 ) by means of one injector condenser ( 20 ) outlet. The steam generator ( 1 ) is fed without using an additional pump for withdrawing feedwater from the storage tank ( 10 ) and for injecting feedwater into the secondary part ( 3 ) of the steam generator ( 1 ). | ||||||
| 56 | PROCEDE ET DISPOSITIF D'ALIMENTATION D'AU MOINS UN GENERATEUR DE VAPEUR D'UN REACTEUR NUCLAIRE A EAU SOUS PRESSION PENDANT LES PERIODES D'ARRET DU REACTEUR | EP02767567.7 | 2002-07-11 | EP1410401B1 | 2008-05-21 | DAGARD, Philippe |
| At least one injector condenser ( 20 ) is used to supply secondary feedwater to the steam generator ( 1 ) during a phase in the course of which the temperature and the pressure of the coolant of the reactor coolant system ( 2 ) of the nuclear reactor are varied between hot shutdown conditions of the nuclear reactor and conditions making it possible to bring into service the residual heat cooling system (RRA). The injector condenser ( 20 ) is fed with steam withdrawn from an upper part of the steam generator ( 1 ), at a first inlet, and with feedwater from a storage tank ( 10 ), at a second inlet. High-temperature pressurized feedwater is supplied to the steam generator ( 1 ) by means of one injector condenser ( 20 ) outlet. The steam generator ( 1 ) is fed without using an additional pump for withdrawing feedwater from the storage tank ( 10 ) and for injecting feedwater into the secondary part ( 3 ) of the steam generator ( 1 ). | ||||||
| 57 | STEAM GENERATION SYSTEM MASS AND FEEDWATER CONTROL SYSTEM | EP92916918 | 1992-04-06 | EP0580798A4 | 1994-07-20 | KIRKPATRICK WILLIAM J |
| 58 | Controlling leaks between primary and secondary circuits of a steam generator of a pressurised water reactor system | EP84308409.6 | 1984-12-04 | EP0146305B1 | 1989-03-08 | Carlton, James D.; Helms, Thomas Christopher |
| 59 | Full range nuclear power plant steam generator level control system | EP87310253.7 | 1987-11-19 | EP0269377A2 | 1988-06-01 | Geets, Jacques Maurice |
A full range steam generator level control system and method is provided by a weighted linear combination of a pair of inputs from a low power and a high power controller to actuate feedwater regulation valves. |
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| 60 | Feedwater control system | EP82300958.4 | 1982-02-25 | EP0067497A2 | 1982-12-22 | Cook, Bruce Michael |
Excessive swing of the feedwater (31) in power supply apparatus on the occurrence of a transient is suppressed by injecting an anticipatory compensating signal (ΔWfw) into the control for the feedwater. Typical overshoot occurs on removal of a large part of the load, the steam flow is reduced so that the conventional control system reduces the flow of feedwater. At the same time there is a reduction of feedwater level in the steam generator (13.15) because of the collapse of the bubbles (125) under increased steam pressure. By the time the control responds to the drop in level, the apparatus has begun to stabilize so that there is overshoot. The anticipatory signal is derived from the boiling power (BP) which is a function of the nuclear power (2N) developed, the enthalpy of saturated water (h.) and the enthalpy of the feedwater injected into the steam generator (hfw). From the boiling power (BP) and the increment in steam pressure resulting from the transient an anticipatory increment of feedwater flow is derived. Thus increment is added to the other parameters controlling the feedwater. |
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