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    • 1. 发明专利
    • ABNORMALITY RELIEVING SYSTEM FOR NUCLEAR POWER PLANT
    • JPH06281784A
    • 1994-10-07
    • JP7012393
    • 1993-03-29
    • TOSHIBA CORP
    • SAKAMOTO YASUNORINISHIYAMA HIROYUKI
    • G21C17/00G21D3/04
    • PURPOSE:To provide an abnormality relieving system for nuclear power plant in which occurrence of abnormality in the compositional machines of plant is detected in early stage, an appropriate operation is determined according to the identification of abnormal point and the extent of abnormality, and then the operation is executed in order to prevent the abnormality from spreading over the plant. CONSTITUTION:The abnormality relieving system for nuclear power plant comprises machine model sections 18a-18n for simulating the operation of each machine constituting the controller for a plant 16 and estimating an output signal from the machine, abnormality detecting sections 19a-19n for making a decision whether the machine is normal or not, a core state monitoring section 20 for monitoring the process amounts of the core, a section 21 deriving an operation for relieving the abnormality of plant based on abnormality decision results, a section 23 for predicting the progress of abnormality and the influence of relieving operation on the plant, a section 24 delivering an operational command to each machine for executing the relieving operation, and a section 22 for displaying abnormality decision results, releasing operation, prediction results, etc.
    • 2. 发明专利
    • CONTROL DEVICE FOR NUCLEAR POWER PLANT
    • JPH05209993A
    • 1993-08-20
    • JP1532392
    • 1992-01-30
    • TOSHIBA CORP
    • SAKAMOTO YASUNORI
    • G21D3/04
    • PURPOSE:To provide a highly reliable computer control device for a nuclear power plant with simple constitution. CONSTITUTION:The operation control device 1 of a nuclear power plant is equipped with a signal inputting section 2 for inputting control and process signals, an input signal diagnosing section 3 for diagnosing an input signal and outputting an alternative demand signal for the control device 1 upon error occurrence, and a normal time control section 4 for generating a normal control signal. Also, the device 1 is equipped with an alternative signal generation section 5 for estimating an alternative value upon error occurrence, an abnormality coping selection section 6 for choosing a logic to cope with an error upon error occurrence and an abnormality coping control section 7 for generating a control signal to cope with the state of abnormality. Furthermore, the device 1 is equipped with an output signal diagnosing section 8 for diagnosing the suitability of a control signal generated in the control section, and demanding an alternative for the capability of the control device 1 upon error occurrence, a signal outputting section 9 for transferring a control signal, when the signal is found suitable, a model section 10 for estimating the operation of an output destination control device, and a output abnormality coping section 11 for diagnosing the operation of the output destination control device via the comparison of an output signal with an estimated operation signal, and outputting an operation demand signal by demanding an alternative for capability upon error occurrence.
    • 4. 发明专利
    • DEVICE AND METHOD FOR OPERATION OF NUCLEAR POWER PLANT
    • JPH03243898A
    • 1991-10-30
    • JP4042690
    • 1990-02-21
    • TOSHIBA CORP
    • SAKAMOTO YASUNORI
    • G21D3/12
    • PURPOSE:To automate output control by providing an automatic flow rate control means which matches the output of a power generator and the flow rate of a reactor core with target values, the power generator, an automatic control rod control means which equalizes the pattern of a control rod to a target value, etc. CONSTITUTION:When an automatic control means 4 for a target output flow rate is selected, the means 4 finds a flow rate adjustment quantity required to equalize the output of the power generator to the target value and sends it to a recirculation flow rate controller 2 to adjust the flow rate of the reactor core, thereby varying the output. When an automatic flow rate control means 5 for a target flow rate is selected, on the other hand, the means 5 finds a flow rate variation speed so that the target reactor core flow rate is reached at scheduled time, and sends a necessary flow rate adjustment quantity to the controller 2 to perform control. When an automatic control rod control means 6 for an output target is selected, the means 6 finds a control rod manipulated variable required to equalize the output of the power generator to the target value and sends it to a control rod driving device 3 to vary the output. Further, when an automatic control rod control means 7 for a control rod pattern is selected, the means 7 determines a control rod operation speed so that a target control rod pattern is reached before scheduled time and sends a necessary control rod manipulated variable to the device 3 to manipulate the control rod.
    • 6. 发明专利
    • System and method of array travel
    • 阵列旅游系统与方法
    • JP2003030777A
    • 2003-01-31
    • JP2001212588
    • 2001-07-12
    • Toshiba Corp株式会社東芝
    • YAMAMOTO JUNKOSAKAMOTO YASUNORISEKI YOSHIRO
    • B60K31/00G08G1/00G08G1/09G08G1/16
    • PROBLEM TO BE SOLVED: To provide an array travel system capable of relieving a burden of a driver. SOLUTION: The array travel system is provided with an on-vehicle device 2 to control automatic travel of a vehicle 200 by providing a lane 102 exclusive for automatic travel, a road facility 3 to guide travel of the vehicle 200 traveling on the exclusive lane 102, a communication facility 4 to perform communication between the on-vehicle device 2 and the road facility 3, the on-vehicle device 2 is provided with an automatic travel switching means 21, an automatic traveling device 22 and a communication means 23 between road and vehicle and the road facility 3 is provided with a vehicle information detecting means 31, an entering vehicle discriminating means 32, a vehicle managing means 33, an array organization determining means 34, a vehicle speed determining means 35 and a communication means 36 between road and vehicle.
    • 要解决的问题:提供能够减轻驾驶员负担的阵列行驶系统。 解决方案:阵列行驶系统设置有车载设备2,通过提供专用于自动行驶的车道102来控制车辆200的自动行驶,道路设施3引导在专用车道102上行驶的车辆200的行驶 作为车载装置2与道路设施3之间的通信的通信设备4,车载装置2设置有自动行驶切换装置21,自动行驶装置22和道路与 车辆和道路设施3设置有车辆信息检测装置31,进入车辆识别装置32,车辆管理装置33,阵列组织确定装置34,车速确定装置35和道路与 车辆。
    • 7. 发明专利
    • METHOD AND SYSTEM FOR VEHICLE TRAFFIC
    • JP2001266286A
    • 2001-09-28
    • JP2000080088
    • 2000-03-22
    • TOSHIBA CORP
    • SAKAMOTO YASUNORIKOYAMA TOSHIHIROSEKI YOSHIRO
    • G08G1/00B60W30/00
    • PROBLEM TO BE SOLVED: To insure the efficient operation of a reserved road. SOLUTION: This vehicle traffic system in which stations 14 are provided along a reserved road 13 on which a convoy of vehicles can be formed, vehicles mutually drive in between the reserved road and an ordinary road 12 and passengers change buses and cars at the stations, is provided with a central traffic controlling device 20 having a convoy travel deciding means 21 for deciding a convoy travel in accordance with whether or not the number of passengers surpasses the number of passenger capacity, a destination deciding means 22 for deciding the destination station of each vehicle organizing the convoy travel and the number of needed vehicles from the number of passengers who get on/off at a station when the convoy travel is decided, a travel road deciding means 23 for deciding which road to travel between the reserved road and the ordinary road as a travel road for a vehicle arriving at the station on the basis of the number of passengers for the reserved road and the number of passengers for the ordinary road after the convoy travel vehicles arrive at the destination station and a vehicle from the ordinary road arrives at the station.
    • 8. 发明专利
    • MONITORING APPARATUS OF REACTOR POWER GENERATION PLANT
    • JPH05134080A
    • 1993-05-28
    • JP29406591
    • 1991-11-11
    • TOSHIBA CORP
    • SAKAMOTO YASUNORIKOBAYASHI YUJI
    • G21C17/00G21C7/08G21C7/26G21D3/12
    • PURPOSE:To obtain a monitoring apparatus of a nuclear power generation plant which executes highly-precise monitoring of a thermal limit value and makes effective use of a computer for other purposes in a period when thermal limit value has a sufficient margin, by updating an operational limit value at short intervals when a change in a core state amount is large and when the margin of the thermal limit value is small and by lessening the frequency of core performance computation when the change is small and when the margin of the thermal limit value is large. CONSTITUTION:A core performance computing device 2 which receives process data as an input and computes a thermal limit value being a condition of limitation imposed on fuel and an operational limit value computing device 3 which receives this thermal limit value and the process data at the time of computation as inputs and computes an operational limit value are provided. Moreover, a thermal limit value monitoring device 4 which receives the operational limit data, the process data at the time of computation of the thermal limit value and process data on the current value as inputs consecutively and monitors the thermal limit value at a high speed, and a determining device 5 which judges the necessity of computation of the thermal limit value by means of the core performance computing device 2 from the result of the monitoring and the process data, such as monitoring process data, at the time of computation of the thermal limit value by the core performance computing device 2, are provided.
    • 9. 发明专利
    • CORE PERFORMANCE CALCULATING APPARATUS
    • JPH0251095A
    • 1990-02-21
    • JP20129288
    • 1988-08-12
    • NIPPON ATOMIC IND GROUP COTOSHIBA CORP
    • SAKAMOTO YASUNORIYOSHIMURA NAO
    • G21C17/00
    • PURPOSE:To enable highly accurate monitoring and forecasting by using a three- dimensional core performance calculation model to correct a quantity of state of a core such as core output, core flow rate and three-dimensional output distribution based on an actual operation data. CONSTITUTION:When an operation is started according to an operation program and a demand for monitoring the condition of a core is inputted from an interactive section 19, a correction method selecting section 12 picks up and compares a quantity of state of a core such as current furnace output, core flow rate and control rod pattern with data preserved at a preliminary calculated value preserving section 11 to select a preliminary calculated value at an operating point the nearest the current quantity of state of core and the preliminary calculated value selected is compared with the current quantity of state of core. When the furnace output and core flow rate are deviated slightly, a first output distribution correcting section 13 is selected to correct a three-dimensional output distribution in preliminary calculation. When the control rod pattern is also deviated due to an action during the course of operation, a second output distribution correcting section 14 is selected. If the core output and core flow rate are deviated significantly, the correction is done by selecting a three- dimensional output distribution correcting section 15.