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    • 14. 发明专利
    • NATURAL CIRCULATION TYPE NUCLEAR REACTOR
    • JPH04122890A
    • 1992-04-23
    • JP24237290
    • 1990-09-14
    • HITACHI LTD
    • MASUHARA YASUHIROTOMINAGA KENJI
    • G21C5/00G21C5/12G21C7/30
    • PURPOSE:To achieve even higher fuel economy by a method wherein a fuel assembly early in the life of fuel is burned at a high output in a Pu production area and the fuel assembly after producing Pu is rearranged to a Pu burning area in the midterm of the life to burn at a low output. CONSTITUTION:The center of a nuclear reactor core 1 is set up as plutonium production area 6 while the peripheral part thereof as plutonium burning area 7. A fuel assembly early in the life of fuel is arranged in the plutonium production area at the center of the reactor core and burned at a high output. On the other hand, when the life of the fuel of the assembly reaches a mid term, the assembly is rearranged to the peripheral burning area and burned at a low output. With such an arrangement, when the operation as mentioned above is performed, plutonium can be produced at the center of the reactor core and the plutonium produced burned at the peripheral part thereby improving the fuel economy by a burned portion of the plutonium.
    • 19. 发明专利
    • WATER ROD AND FUEL ASSEMBLY
    • JPH01176982A
    • 1989-07-13
    • JP36988
    • 1988-01-06
    • HITACHI LTD
    • NAKAO SHUNJIYOKOMIZO OSAMUMASUHARA YASUHIROKASHIWAI SHINICHITOMIYAMA AKIONISHIDA KOJIYAMASHITA JUNICHI
    • G21C3/326G21C3/32
    • PURPOSE:To easily and stably control the void rates in a reactor core by a change in the flow rate within the core by providing a coolant rising flow passage having an inflow port in the position lower than a resistor and a coolant descending flow passage having a discharge port in the position upper than the resistor. CONSTITUTION:This fuel rods consists of a riser 21, a downcomer 31, a branch fitting 11, upper, lower caps 15, 16, etc. A hole 12 having a bottom in the central part is provided to the fitting 11 and holes 13 to discharge the cooling water to 4 ways from the bottom of the hole 12 are provided. The upper part of the hole 12 is butt-welded to the downcomer 31. The riser 21 is welded to the top of the outside circumferential part of the fitting 11 and the cap 16 to the bottom of said part. A hole 14 is penetrated in the fitting 11 so as to avert the hole 13. The cooling water enters the inflow port 4, rises in the flow passage 2 by passing the hole 14 and enters the flow passage 3 from a communicating port 10 provided to the upper part of the downcomer 31 in which the cooling water flows downward until the water is discharged from the holes 12, 13. The downcomer 31 is formed of a niobium alloy or 347 stainless steel. The change in the void rates with respect to an increase in the differential pressure between the inlet and the outlet is more monotonous as the bore of the downcomer 31 is smaller. The void rates are thus equivocally determined with respect to the differential pressure between the inlet and the outlet.
    • 20. 发明专利
    • CORE INTERNAL STRUCTURE OF NUCLEAR REACTOR
    • JPS646892A
    • 1989-01-11
    • JP16267687
    • 1987-06-30
    • HITACHI LTD
    • MASUHARA YASUHIROYOKOMIZO OSAMUMOCHIDA TAKAAKIKASHIWAI SHINICHITOMIYAMA AKIONAKAO SHUNJI
    • G21C3/326G21C3/32G21C7/28
    • PURPOSE:To increase burnup and to improve fuel economy by decreasing a difference in reactivity during the operation and shut-down of a nuclear reactor and increasing the reactivity during the operation. CONSTITUTION:The top end of a neutron moderating pipe 6 filled internally with an inert gas is closed and a communicating hole 4 for opening the bottom part is provided thereto. An internal piping 7 running through the top end and bottom end of the neutron moderating pipe is provided and a moderator is passed in this piping 7. Fins 8 for steam condensation are provided in the upper part. Double pipes or an internal pipe provided with a spray part in the upper part which is not the through-piping 7 is equally satisfactory. The inert gas is thereby compressed by cooling water and the neutron is moderated over the entire length of the fuel rod during the normal operation. The average density in the pipe is decreased during the shut-down of the reactor. The difference in the reactivity during the shut-down and the operation is thereby eliminated and, therefore, the uranium to water ratio during the operation is increased and the reactivity during the operation is improved; in addition, there are no moving parts and, therefore, the reliability is enhanced.