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    • 2. 发明专利
    • REFUSE INCINERATION PLANT AND CONTROL METHOD THEREOF
    • JP2000205541A
    • 2000-07-25
    • JP1030099
    • 1999-01-19
    • HITACHI LTD
    • KONO TAKESHITANIGUCHI MASAYUKIYAMAMOTO KENJIKAWABE RYUHEITAKEGAWA SHIGEKI
    • F23G5/50
    • PROBLEM TO BE SOLVED: To reduce emission of environmental pollution substances in exhaust gas quickly by correlating the air ratio of thermal decomposition gas produced from the drying stage with the concentration of environmental pollution substances and controlling an incinerator to minimize the concentration of environmental pollution substances according to the correlation. SOLUTION: A gas concentration sensor 27 disposed on a dry stoker 4 measures oxygen and the composition of unburnt components contained in combustion gas. An air ratio operating unit 28 calculates the air ratio from the mass fraction of carbon atom, hydrogen atom and oxygen atom contained in the combustion gas based on the oxygen and the composition of unburnt components. A thermal decomposition gas temperature sensor 26 measures the temperature of thermal decomposition gas produced from above the dry stoker 4 and outputs the measurements to a flow rate distribution controller 30. The flow rate distribution controller 30 controls the incinerator to minimize the concentration of environmental pollution substances according to the relationship of the concentration of various environmental pollution substances, the air ratio of thermal decomposition gas obtained from the air ratio operating unit 28, and the temperature of thermal decomposition gas.
    • 7. 发明专利
    • CORE FLOW MEASUREMENT OF LIQUID METAL COOLING NUCLEAR REACTOR
    • JPH04204091A
    • 1992-07-24
    • JP32907090
    • 1990-11-30
    • HITACHI LTD
    • KAWABE RYUHEI
    • G21C17/032
    • PURPOSE:To contrive improvement of accuracy and safety by attaching a flow meter which connects a secondary cooling water system and a water system, to an intermediate heat exchanger, and a liquid surface meter to pump surroundings, respectively, as a heat transferring system. CONSTITUTION:A coolant sodium comes out of a reactor core 1, flows into each intermediate heat exchanger 3 via a high temperature prenum 2, and then enters a low temperature prenum 4 and returns to the reactor core 1 again via a pump 5 and a pump discharge pipe 6. At an outlet of the heat exchanger 3, an insodium electromagnetic flow meter 7 is provided and also a liquid surface meter 8 measures sodium liquid surface 9 which is formed at the pump surroundings. Core flow rate Wc is obtained by the equation I from the measured values of the flow meter 7 and the liquid surface meter 8. Here, Wi is flow rate of the i-th intermediate heat exchanger, Sj is the j-th liquid surface area, Lj is the j-th liquid surface level and t is the time. By this treatment, linearity of flow rate-output relation is improved, and highly accurate measurement and improvement of safety are contrived.
    • 9. 发明专利
    • PRESSURE TUBE NUCLEAR REACTOR
    • JPS6483187A
    • 1989-03-28
    • JP23873887
    • 1987-09-25
    • HITACHI LTD
    • KAWABE RYUHEIYAMAKI RIKA
    • G21C1/20
    • PURPOSE:To prevent breaking of reactor core fuel in the case where an emergency core cooling system cannot be operated by performing manufacture for increasing radiation rate on the inwall of a calandria tube. CONSTITUTION:A tube housed in a fuel assembly is dual and composed of a pressure tube 1 in the inside and a calandria tube 2 in the outside. Carbon dioxide is enclosed in the annular space between dual tubes, and the function for insulating the high temperature pressure tube 1 and the ordinary temperature calandria tube 3 is performed thereby. Autoclave treatment of the outer surface of the pressure tube 1 is performed to prevent oxidation corrosion and the like of the surface thereof. Further, radiation rate is increased and the quantities of heat transfer to the pressure tube 1 of high temperature fuel, the calandria tube 3 and heavy water 4 are enlarged by performing autoclave treatment on the inwall of the calandria tube 3. Therefore, cooling of fuel rods can be performed in the case of coolant loss accident.
    • 10. 发明专利
    • STEAM GENERATOR PLANT
    • JPS6472096A
    • 1989-03-16
    • JP22840087
    • 1987-09-14
    • HITACHI LTD
    • SANO KENJIKAWABE RYUHEIMURATA SHIGETOAOYAMA GORO
    • F22B1/06F22B1/16F22B37/26G21C15/18
    • PURPOSE:To remove decay heat by detecting the pressure difference between the inlet and outlet of a recirculation flow passage valve, then by opening a spray supply valve to assure water in a steam separator when the detection signal attains a set differential pressure and by opening the recirculation flow passage valve when the water level in the separator attains a set water level. CONSTITUTION:The steam from a steam generator 1 after tripping of a nuclear reactor flows through a bypass valve 18 and a feed water heater 9 to a condenser 6 by bypassing a turbine 5. Since the flow rate of the feed water decreases, the differential pressure across the recirculation flow passage valve 14 increases from the negative toward the positive pressure. The differential pressure signal by a differential pressure detector 30 is inputted to a control circuit 31 and is compared with the set differential pressure. The spray supply valve 13 is opened when the differential pressure signal exceeds the set differential pressure. The feed water is then sprayed through a spray supply pipe 23 into the steam separator 4 by a nozzle 4 and is stored in the separator 4. The water level in the separator 3 is monitored by a water level gage 35. The valve 14 is opened by ANDing with the the open signal of the valve 13 when the monitored water level exceeds the set water level. The entire part of the system is thus maintained at the saturation temp. of water.