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    • 1. 发明专利
    • FUEL ASSEMBLY
    • JPH02198393A
    • 1990-08-06
    • JP1616289
    • 1989-01-27
    • HITACHI LTD
    • NAKAO SHUNJIYOKOMIZO OSAMUKASHIWAI SHINICHITOMIYAMA AKIONISHIDA KOJIORII AKIHITO
    • G21C3/326G21C3/32G21C7/27
    • PURPOSE:To facilitate control of a void rate of a reactor core by providing a fuel assembly with a coolant passage connected to a coolant discharge opening, a coolant climb passage connected to a lower region and a coolant drop passage connected to the coolant passage. CONSTITUTION:A great part of cooling water fed to a fuel assembly 20 is introduced to a passage 23 of the fuel assembly 20 through a through hole 18 provided in a fuel hold part 16 of a lower tie plate, and the residual cooling water is allowed to flow in a water rod 31. Part of the cooling water allowed to flow in an inflow port 19 is introduced in a coolant passage 8 from a flow opening 7 to reach a space 12. The residual cooling water allowed to flow in an inflow opening 19 is allowed to flow in a coolant climb passage part 2 through a coolant climb passage part inlet 4 to be discharged in the passage 8 from a drop passage discharge opening 5 through a reversion part 15 and a coolant drop passage part 3 further. The cooling water discharged from the discharge opening 5 becomes liquid or gas in accordance with the flow amount of the cooling water allowed to flow in the passage 8 from a passage opening 7.
    • 8. 发明专利
    • WATER ROD AND FUEL ASSEMBLY
    • JPH01176984A
    • 1989-07-13
    • JP37988
    • 1988-01-06
    • HITACHI LTD
    • KASHIWAI SHINICHIYOKOMIZO OSAMUMASUHARA YASUHIRONAKAO SHUNJITOMIYAMA AKIONISHIDA KOJIYAMASHITA JUNICHI
    • G21C3/326G21C3/32
    • PURPOSE:To easily and stably control and largely change the void rates in a nuclear reactor by a change of the flow rate in the core with a simple construction by working the inside surface of a riser so as to form foaming nuclei. CONSTITUTION:The foaming nuclei are provided on the inside wall of a rising flow passage 2 (outside surface of a downcomer 31) and outside wall (inside surface of the riser 21) of a water rod. Stable continuous boiling is thereby generated and the fluctuation in the liquid level (void) in the water rod is decreased. The temp. of the downcomer 31 upper than a liquid surface is increased as the downcomer is heated by irradiation of neutrons and gamma rays if there is the liquid surface exists in the flow passage 2. On the other hand, the reactor output increases sharply when the core flow rate increases and the void rates drop sharply. The liquid surface touches the metal overheated in a steam section and hinders the abrupt change of the liquid surface (void) when the core flow rate increases sharply and is going to lift the liquid level in the water rod. The heat transfer area is increased as well by the foaming nuclei at this time and, therefore, the effect of hindering the abrupt increase in the reactor output increases as well.
    • 9. 发明专利
    • NUCLEAR REACTOR CORE SUBSTRACTURE
    • JPS6418094A
    • 1989-01-20
    • JP17547787
    • 1987-07-14
    • HITACHI LTD
    • KASHIWAI SHINICHIYOKOMIZO OSAMUNAKAO SHUNJIMASUHARA YASUHIROTOMIYAMA AKIO
    • G21C15/02
    • PURPOSE:To reduce cooling water pressure loss of a reactor core inlet part without drastic modification of reactor structure elements and drastic increase of equipment cost by setting dimensions and position of opening, which is a fuel support fitting cooling water passage inlet on the upper part of a control rod guide pipe, in a fixed condition. CONSTITUTION:Vertical direction length of opening 30 which is an inlet of a fuel support fitting cooling water passage 5 of a control rod guide pipe 16 reaches at least up to the lower surface of a core plate 3 from the position at which a fuel support fitting 15 is inscribed on the control rod guide pipe 16 and its width is at least equal to the hole diameter of perforated seat of the fuel support fitting 15. The circumferential position of the fuel rod guide pipe 16 of the opening 30 indicates the position at which the hole of the perforated seat includes the projected position on the pipe wall of the control rod guide pipe 16 from the center side of the fuel support fitting 15. Therefore, the curvature of the fuel support fitting cooling water passage 5 is moderate, pressure loss of the cooling water can be lessened and the reactor core flow can be increased without enlarging pump capacity.