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    • 2. 发明专利
    • VAPOR LEAK MONITORING DEVICE
    • JPS6472025A
    • 1989-03-16
    • JP22858687
    • 1987-09-14
    • NIPPON ATOMIC IND GROUP COTOSHIBA CORP
    • SANO KENICHIKOYAMA KAZUHIKOKOJIMA AKIRA
    • G01M3/24
    • PURPOSE:To discriminate between vibration due to a vapor steam and other vibration by separating a detection signal from a vibration detector into plural frequency components and comparing the level ratio of the respective frequency components with a reference set value. CONSTITUTION:The detection signal of the vibration detector 1 is passed through a preamplifier 2 and a main amplifier 3, then passed through a frequency component separator consisting of plural BPFs 4, and converted 5 into effective values. They are A/D-converted 6 and then inputted to a microcomputer 7. The microcomputer 7 is stored with power levels of the respective frequency components at the time of a background noise or vapor leak and their total power level, and set values for detecting variation are provided above and below the total power level of the respective frequency components based on the total power level. Then it is decided whether or not the power of each smoothed frequency component exceeds the set values. When there is a frequency component exceeding the set values, a decision is made according to the fact that the background noise has many low frequency components and the vapor leak has many high frequency components; when leak occurrence is decided, a warning is displayed 8.
    • 8. 发明专利
    • CONTROL ROD DRIVING/CONTROLLING DEVICE
    • JPH01244393A
    • 1989-09-28
    • JP6961988
    • 1988-03-25
    • TOSHIBA CORP
    • KOJIMA AKIRA
    • G21C7/08G21C7/26G21C7/27
    • PURPOSE:To hold a reactor core condition stable in operation at the time of spectrum shift operation and widen an operation range by selecting a value of higher flow rate among values indicated by intersecting points of a recirculating weight control curve and 100% output as the lower limit of the flow rate of spectrum shift operation. CONSTITUTION:The output distribution of a reactor core is obtained from the result in which the signals of a reactor neutron detector 13 are input in an output distribution measuring device 15 through a localized output range monitor system 14A and an average output range monitor 14B. The output of the output distribution measuring device 15 is input in a block 1. In the block 1, the output distribution is estimated when the pump speed is descended lower than the present output, a recirculating flow control curve for holding sufficient stability at the time of the maximum output of lowest pump speed and the lower limit of automatic flow is obtained from a stable line calculating program and a recirculating flow control curve calculating program, further the intersecting point of it and 100% output is obtained and larger flow rate is set as the lower limit of the spectrum shift operation to output in a block 2. The block 2 outputs a control rod pulling prevention signal on the basis of the lower limit of the flow.
    • 10. 发明专利
    • CONTROLLING DEVICE OF RECIRCULATION FLOW RATE OF BOILING WATER NUCLEAR REACTOR HAVING FULL BYPASS SYSTEM
    • JPH03251797A
    • 1991-11-11
    • JP4824590
    • 1990-02-28
    • TOSHIBA CORP
    • KOJIMA AKIRA
    • G21D3/04
    • PURPOSE:To maintain a stability of reactor core part and to enable maintaining a low power operation by reducing a rotation of a recirculation pump to the lowest allowable flow rate at an occasion of a generator load to be cut off, and by tripping the pump at an occasion of failed run-back operation. CONSTITUTION:In case that a generator load is cut off 1 when a nuclear reactor output is higher than a specific value, the reactor output is made to decrease 7 by reducing rotation of a recirculation pump to a rotation speed giving the lowest allowable flow rate of the pump by inserting 5 selective control rods and by running-back 40 of the circulation pump. Moreover, when the running- back of the recirculation pump is failed 41 or turbine by-pass valves do not work 8, the nuclear reactor is made to scram 10 and the recirculation pump is made to trip 6, as well. With these procedures, an operation under a natural convection condition which is less stable for a reactor core part, can be avoided, during sudden closing 3 of a turbine control valve and sudden opening 4 of a turbine by-pass valve, and therefore a low output operation can be maintained.