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    • 3. 发明专利
    • WITHDRAWAL OF FUEL ROD
    • JPS6450995A
    • 1989-02-27
    • JP20635287
    • 1987-08-21
    • HITACHI LTDHITACHI ENG CO LTDHITACHI SERVICE ENGHITACHI NUCLEAR ENG
    • SEYA TORUTOKUNAGA KENSUKEGOTO FUMIHIROSEYA SATOSHI
    • G21C19/33
    • PURPOSE:To enable an easier withdrawal of fuel rod, by giving an impact energy by a spring or pneumatic pressure directly to a lower end plug of a fuel rod and by lifting up the fuel rod upwardly to push the fuel rod up from its lower most part and to release it from sticking with other parts. CONSTITUTION:By moving and setting a fuel assembly to and in a fuel channel handling machine 11, by setting previously an angle of a nail 15 of a pneumatic driven fuel rod withdrawal jig 14 at a corresponding position of a fuel rod to be withdrawn, by lifting the jig 14 by jibcrane and by attaching setting guide 16 to a lower receiving table 12 of the machine 11, the nail 15 can be set to a lower part of a lower end plug of fuel rod to be withdrawn. Consequently, air from a baby compressor 17 is led to a piston 20 of a cylinder, a notch 21 is lifted up by an energy of a spring 23 with decoupling of the notch 21 and a movement of the notch 21 is transferred to a rod 24 as an impact energy and finally the nail 15 pushes up the lower end plug of the fuel rod. The lifted-up fuel rod is grasped by a rod grapple and the rod is withdrawn from the fuel assembly with the descending channel handling machine 11 after removal of the withdrawal jig.
    • 6. 发明专利
    • METHOD FOR CHARGING FUEL ASSEMBLY
    • JPH02161390A
    • 1990-06-21
    • JP31390288
    • 1988-12-14
    • HITACHI LTDHITACHI ENG CO LTD
    • MATSUURA TETSUAKITOKUNAGA KENSUKEOKUDA SHINICHINAKAI KEIICHI
    • G21C5/00G21C19/19
    • PURPOSE:To make effective utilization of channel boxes by making predictive calculation of the difference in the irradiation quantity of fast neutrons on two opposite side faces of all the channel boxes in operation and evaluating the interference of the channel boxes and control rods. CONSTITUTION:The fast neutron fluxes phi of all the fuel assemblies are calculated by using predictive calculation codes with respective cycles and the inclinations DELTAphi of the fast neutrons between the two opposite side faces of the channel boxes (CB) are determined and are multiplied by the irradiation time of the respective cycles, by which DELTAphi.t of all the CBs in the core at the end of the respective cycles are calculated. The DELTAphi.t are compared with phic.t having the possibility that the CBs interfere with the control rods and if there is the CB which attains DELTAphi.t>DELTAphic.t, such CB is exchanged with the CB in the position having such DELTAphi at which bending arises in a reverse direction. The optimum fuel charge position at which the number of the CBs to attain DELTAphi.t>DELTAphic.t are minimized is determined by repeating the above-mentioned procedures. Thus the CBs are utilized effectively.