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    • 1. 发明专利
    • REACTOR INTERNAL EQUIPMENT ELEVATING DEVICE
    • JPH1164570A
    • 1999-03-05
    • JP22502197
    • 1997-08-21
    • TOSHIBA CORP
    • FUKAMICHI KENJIROAKIMOTO ATSUSHI
    • G21C19/02B66C1/10B66C1/62B66C13/08B66C17/04
    • PROBLEM TO BE SOLVED: To provide a reactor internal equipment elevating device safe and high in reliability by further ensuring the support function of the elevating device for taking out reactor internal equipment from a reactor pressure vessel to transfer it at the time of periodic inspection and fuel replacement of a boiling water reactor in nuclear power installations. SOLUTION: A reactor internal equipment elevating device for lifting reactor internal equipment from above a reactor and moving it to an equipment storage pool or the like is provided with an upper beam 59 lifted by an overhead crane or the like, a lower beam for attaching/detaching the reactor internal equipment, an approaching/separating action means for putting the upper beam 59 and lower beam in approaching/separating action along a vertical direction, and a contact means for stopping the upper beam 59 and lower beam in a specified approach direction. The contact means is composed of a jack body 70 installed on the upper face side the lower beam so as to be put in elevating action, and a jack receiving body 71 provided on the lower face side of the upper beam 59 so as to receive the jack body 70. An approach position between the upper beam 59 and lower beam can therefore be adjusted.
    • 2. 发明专利
    • FUEL HANDLING MACHINE
    • JPH01152399A
    • 1989-06-14
    • JP31098387
    • 1987-12-10
    • TOSHIBA CORP
    • AKIMOTO ATSUSHI
    • G21C19/19
    • PURPOSE:To ease the maintenance of a fuel handling machine by providing reactor instrumentation at the position without interference with a setting position of a gripper and rotating a hold-down cylinder for holding a gripper and an instrumentation column for holding reactor instrumentation. CONSTITUTION:In the time of rated output operation, reactor instrumentation 120 is positioned at a prescribed position of a reactor core side by a fuel handling machine and a small rotating plug 4 and the instrumentation of a reactor core component outlet is performed. In the time of fuel exchange the reactor instrumentation 120 is positioned in a reactor core component top by the rotating plugs 3, 4 and own rotation, a gripper 104 is driven and handling of the reactor core component is performed. In the time of maintenance, a column 121 and a hold-down cylinder 102 are rotated on the periphery of respective center axis, a whole fuel handling machine rotating housing 101 is pulled upward and the maintenance is performed.
    • 4. 发明专利
    • REFUELING DEVICE FOR NUCLEAR REACTOR
    • JPH03259798A
    • 1991-11-19
    • JP5650090
    • 1990-03-09
    • TOSHIBA CORP
    • AKIMOTO ATSUSHI
    • G21C19/02G21C19/19
    • PURPOSE:To prevent an increase in the size over the entire part of a reactor by the increased size of a rotating plug by carrying out a fuel assembly to be taken out of the relay point in a reactor core fuel region by means of a refueling machine with an offset arm suspended to the rotating plug. CONSTITUTION:The upper aperture of a reactor vessel 1 housing the reactor core is covered by a stationary plug 2 and a mechanism 4 in the upper part of the reactor core is mounted to the rotating plug 3 which is freely rotatably mounted to the center of this plug 2. The fuel transfer machine 5 with the offset arm which is provided in a slit 4c of this mechanism 4 and is equipped with a CCD camera is constituted freely movably from the center of the reactor core 7 to the outermost side of the reactor core fuel region 10. The fuel of this region 10 can be transferred to the outside of the reactor core 7 via the provided relay point 8 by the combination use of the rotation of the mechanism 4 and the movement of the transfer machine 5. The diameter of the plug 3 is thus made smaller than the max. outside diameter of the reactor core 7 and the simple and small-sized plug suffices.
    • 5. 发明专利
    • REACTOR BOTTOM PART SHIELDING BODY FOR NUCLEAR REACTOR PREVENTIVE MAINTENANCE
    • JPH11133185A
    • 1999-05-21
    • JP29591797
    • 1997-10-28
    • TOSHIBA CORP
    • AKIMOTO ATSUSHIWATANABE YUSUKE
    • G21D1/00G21F1/04G21F3/00
    • PROBLEM TO BE SOLVED: To provide a reactor bottom part shielding body for nuclear reactor preventive maintenance enabling workers to work on a reactor bottom part, enabling installation to be conducted easily and surely, and enabling a shielding function to be maintained sufficiently by co-operation with interfering objects existing on the reactor bottom part, by shielding out surely radiation coming upward from the bottom part of a drained unclear reactor pressure vessel. SOLUTION: A reactor bottom part shielding body 11 screens out radiation coming upward from crud remaining on surfaces of a control-rod drive mechanism housing 14 and on an inner surface of a lower end plate 15 of a nuclear reactor pressure vessel, in the event of preventive maintenance work on and around a reactor bottom part within the nuclear reactor pressure vessel 1 in a boiling water reactor. The shielding body 11 is equipped with a flat plate-like screening body proper 12 composed of metal or a material made by combining metal with concrete and inserted substantially horizontally into a shroud support cylinder 13, and stands 17 provided on the screening body proper and supported by the reactor bottom part in co-operation with existing objects such as the control-rod drive mechanism housing 14.
    • 6. 发明专利
    • SHROUD HEAD BOLT OF BOILING WATER REACTOR
    • JPH09281276A
    • 1997-10-31
    • JP9256396
    • 1996-04-15
    • TOSHIBA CORP
    • AKIMOTO ATSUSHI
    • G21C13/02G21C19/02
    • PROBLEM TO BE SOLVED: To improve the handling operability by engaging the engagement groove of a nut lock member with the engagement projection of a clamping nut through self-orientation operation. SOLUTION: The nut lock member 28 is fitted onto the lower side of the clamping nut 27 which engages a screw shaft part. The nut lock member 28 is always pressed against the clamping nut 27 by the coil spring 29 fitted onto the lower end. The clamping nut 27 has the engagement projection formed at the end part on the side of the nut lock member 28 and the nut lock member 28 has the engagement groove 31, engaging the engagement projection 30, at the end part on the side of the clamping nut 27. The engagement groove 31 has a tapered surface 31a formed on its external surface and the engagement projection 30 has a tapered surface 30a on its flank. When the tapered surface 30a comes into contact with the tapered surface 31a, the tapered surface 31a slides along the tapered surface 30a and a curved surface with the pressing force of the coil spring 29 and the engagement projection 30 is so guided as to automatically engages one of engagement grooves 31.
    • 7. 发明专利
    • REACTOR IN-CORE GUIDE DEVICE
    • JPH09127285A
    • 1997-05-16
    • JP28354995
    • 1995-10-31
    • TOSHIBA CORP
    • FUKAMICHI KENJIROAKIMOTO ATSUSHI
    • G21C19/02
    • PROBLEM TO BE SOLVED: To raise reliability by surely detecting the state that the lower end of an upper guide rod member is loaded in a stud. SOLUTION: The lower end of an upper guide rod member 16 provided inside a reactor pressure vessel 1 is loaded in the stud 19 of a lower guide rod member 17 in this in-core guide device of a reactor. In the upper guide rod member 16, a dry battery 25, a light, a reflection mirror 26, a limit switch electrically connecting to the dry battery 25 and an operation rod 37 freely contacting the limit switch are provided. In the upper guide rod member 16, a window 22 for transmitting the light from the light 23 is provided. When the upper guide rod member 16 is inserted in the stud 19, it detects the displacement of the both, the limit switch is turned on, current flows from the dry battery to the light 23 and the light 23 turns on. This is confirmed with the light from the window 22 to confirm the loading state.
    • 8. 发明专利
    • CLEANING APPARATUS FOR COOLING SYSTEM OF RECIRCULATION PUMP MOTOR IN NUCLEAR REACTOR
    • JPH0836085A
    • 1996-02-06
    • JP17150394
    • 1994-07-25
    • TOSHIBA CORP
    • KATAYAMA KENJIROKONDO TAKAHISAFUKAMICHI KENJIROAKIMOTO ATSUSHI
    • G21C19/307
    • PURPOSE:To keep the work space without installing a cyclone separator and clean all the flow route of motor cooling water by installing a cap body to separate the inside of a motor casing in the upper end of a motor casing and the inside of a nuclear reactor pressure container. CONSTITUTION:A cleaning water supplying pump 42 and a filter 43 to filter the cleaning water are installed in the outside of a motor casing 5. In the case where a motor cooling system 12 is cleaned, the motor part in the motor casing 6 and a pump part in the nuclear reactor pressure container 1 are taken away. With this condition, the cleaning water supplying pump 42 and the filter 43 are installed and cleaning water is circulated to the whole motor cooling system, so that foreign substances can be recovered surely. The cleaning water is circulated while the inside of the motor casing 6 is shielded from the inside of the pressure container 1 by installing a cap body 44 and an independent cooling water supplying pump 42 is installed, so that cleaning can be carried out independently of the cooling water of the nuclear reactor and thus the flow rate of the cleaning water can be set to be larger flow rate at the time of cleaning than that at the time of driving for motor cooling.
    • 9. 发明专利
    • REFUELLING DEVICE
    • JPH0329893A
    • 1991-02-07
    • JP16378589
    • 1989-06-28
    • TOSHIBA CORP
    • FUJIKI KENJIAKIMOTO ATSUSHI
    • G21C19/19
    • PURPOSE:To make a handling machine more compact by using a telescopic fuel transporting machine. CONSTITUTION:A shielding plug of a nuclear reactor vessel has a greater rotary plug provided at a fixed plug, and a smaller rotary plug provided at the greater rotary plug at its eccentric position. To the smaller plug, a fuel transfer machine 15 which handles core constituting elements located in an inner side of a relaying point, is provided, and also to the greater rotary plug, a refuelling machine which handles core constituting elements located in an outer side of the relaying point, is provided. To this transfer machine 15, a gripper 25 for gripping the core constituting elements is provided at its end tip, and the gripper can be axially extended or constituting by a gripper support tube 24 and an upper support tube 23. Accordingly, a maintenance work can be conducted by reducing an axial length and by removing from the smaller rotary plug, and therewise it can be intended to make the handling machine more compact. Also, by providing a coolant temperature instrumentation for outlets of the core constituting elements which panetrate the support tubes 23 and 24 at a periphery of the gripper 25, a detection of a coolant temperature whole through a nuclear reactor operation can be reasonably conducted.
    • 10. 发明专利
    • FUEL EXCHANGER FOR FAST BREEDER
    • JPS63269098A
    • 1988-11-07
    • JP10186787
    • 1987-04-27
    • TOSHIBA CORP
    • AKIMOTO ATSUSHI
    • G21C19/19
    • PURPOSE:To simplify an attachment, by arranging a pantagraph mechanism suspended with one end thereof supported at the bottom of a vertically movable housing to turn upward from the lowest part thereof so that interference with other components within a reactor is decreased during the movement thereof. CONSTITUTION:A fuel exchanger is provided with a pantagraph mechanism, one end of which is supported at the bottom of a vertically mobile housing 8 and the other end thereof is moved radially with upward rotation thereof from the lowest part thereof within a vertical plane centered on support points 19a and 19b. Then, a slewing driver 49 is driven to operate a locking device 45 only when a pantagraph 8 moves vertically while making a circumferential positioning. A pantagraph arm 21 for diametrical positioning is reduced or extended gradually by repeating operation of extending the arm finely to avoid interference with other core components and that of vertically moving the vertically mobile housing 8 corresponding to this action to convey the core components to a specified position. The components 5 thus conveyed are separated.