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    • 17. 发明专利
    • OPERATION METHOD OF REACTOR
    • JPS5439791A
    • 1979-03-27
    • JP10614977
    • 1977-09-02
    • HITACHI LTD
    • OOSUMI KATSUMIMIKI MINORU
    • G21D3/08G21C7/00G21C19/28
    • PURPOSE:To prevent the generation of stress corrosion cracking and to improve the safety, by means os allowing the dissolved oxygen concentration degree and the dissolved hydrogen peroxide concentration degree in the coolant within a reactor vessel when the reactor is in the transiting operation time of start or stop. CONSTITUTION:The starting of a reactor due to the withdrawing of the control rod, is allowed to be started after a vacuum of a condenser 15 is attained, and after the dissolved oxygen concentration degree in the cooled water of the reactor vessel 6 becomed below a prescribed value (about 0.2 ppm.) by means of operating a venting of 2-4 hours in an opened state of a by-pass valve 21 of a turbine of a turbine by-path line 9 connected to a main drain line 10 and at the same time to a main steam separating valve 8 and a main steam line 7 without interposing of turbines 13, 14. And for the purpose of preventing the termporal uprising of the concentration degrees of hydrogen peroxyde and oxygen of the core water immediately after the starting, the neuclear heating is started after the core water to be raised at about 150 deg.C by the heating of a pump after the venting operation.
    • 19. 发明专利
    • LOAD FOLLOW-UP CONTROL OF BOILING WATER TYPE NUCLEAR POWER GENERATION PLANT
    • JPS63279199A
    • 1988-11-16
    • JP11346487
    • 1987-05-12
    • HITACHI LTD
    • YAGI HIROYUKIHIROSE MASAOMIKI MINORU
    • G21D3/12
    • PURPOSE:To achieve a load follow-up operation without lowering generation efficiency so much in a boiling water type nuclear reactor of natural circulation, by providing a bypass line to a condenser via a bypass valve for output control and a feed heater from a main steam pipe. CONSTITUTION:In a power generation plant which uses a boiling water type nuclear reactor 1 (of natural circulation) having no control means of a core flow rate, steam of a main steam pipe 13 is sent to a turbine 3 via a steam control valve 10 and circulated to the reactor 1 via a pump 4, a water feed pipe 36 and the like after being condensated with a condenser 2. A turbine bypass line 12A is provided to send steam of the main steam pipe 13 to the condenser 2 via a turbine bypass valve 12 for output control and a feed heater 35. The opening of the valve 12 is adjusted according to a load follow-up signal 20, thereby allowing a load follow-up control without affecting a nuclear reactor pressure remarkably. Steam sent to the condenser 2 through the valve 12 restores heat energy to feed water with the feed heater 35 in the course thereof, thereby preventing the lowering of generation efficiency.