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    • 2. 发明专利
    • SAFETY DEVICE FOR NUCLEAR REACTOR
    • JPH03128491A
    • 1991-05-31
    • JP17805989
    • 1989-07-12
    • TOSHIBA CORP
    • SUMIYAMA SHIGEAKI
    • G21C9/033
    • PURPOSE:To improve the reliability of the nuclear reactor by utilizing a magnetic fluid pump which has no mechanical movable part as a neutron absorber injection pump. CONSTITUTION:When the safety device is actuated, an explosion valve 18 explodes to open and magnetic fluid which is pressurized with the necessary gas in a storage tank 16 and contains atoms large in heat neutron absorption sectional area is passed through a magnetic fluid pump 17 and the explosion valve 18 in the open state and injected into the reactor 13 to operate as a neutron absorber, thereby decreasing the output of the reactor 13. The steam in the reactor 13, on the other hand, is admitted to the pump 17 and applied to a magnetic field applied to the fluid 15 running through the pump 17 to generate a temperature difference. Consequently, the fluid 15 is raised in pressure. Therefore, the fluid 15 as the neutron absorber in the storage tank 16 is injected speedily into the reactor 13 by a large amount with the necessary gas pressure in the storage tank 16 and the discharging force of the pump 17, so atoms in the fluid 15 absorb neutrons in the reactor 13 to stop the operation of the reactor 13. Thus, the pump 17 has no mechanical movable part, so the reliability is improved correspondingly.
    • 5. 发明专利
    • CONTROL DEVICE FOR DENSE GRID BOILING WATER REACTOR
    • JPH01105195A
    • 1989-04-21
    • JP26303387
    • 1987-10-19
    • NIPPON ATOMIC IND GROUP COTOSHIBA CORP
    • SUMIYAMA SHIGEAKI
    • G21C7/00G21C7/26
    • PURPOSE:To enable the control of reactor output and to improve safety while assuring the sufficient thermal safe allowance of reactor core cooling by making combination use of a core flow rate change and control rod position change in controlling the reactor output. CONSTITUTION:The core of the dense grid boiling water reactor is constituted of fuel assembles disposed with many fuel rods in a dense grid state and the reactor output is controlled according to an output request signal. An arithmetic circuit 11 for the control rod position and core flow rate request calculates the core flow rate change quantity and the control rod position change quantity in such a manner that the relation between the reactor output and the core flow rate after the change does not deviate from a line for monitoring the fuel heat flow flux. Then, the circuit transmits the core flow rate request signal corresponding to the core flow rate change quantity to a speed controller 25 of a recirculation pump 29 and outputs the control rod position change signal corresponding to the control rod position change quantity to an operating circuit 22 for control rod selection. The reactor output is controlled by making combination sue of the core flow rate change and the control rod position change.
    • 6. 发明专利
    • ATOMIC REACTOR SIMULATOR
    • JPS61198370A
    • 1986-09-02
    • JP3763785
    • 1985-02-28
    • NIPPON ATOMIC IND GROUP COTOSHIBA CORP
    • ARAI KENJISUMIYAMA SHIGEAKI
    • G21C17/00G06F19/00
    • PURPOSE:To improve the training efficiency by displaying the result of analysis from an atomic reactor characteristic analysis section through animation to make the transition of phenomenon relating to the thermohydraulic behavior in an atomic reactor pressure vessel to each trainee understood. CONSTITUTION:The result of analysis relating to the dynamic characteristic such as void rate of an operating fluid, fluid state of the operating fluid, pressure of atomic reactor and surface temperature of fuel rod coating tube with respect to the thermo hydraulic behavior in the atomic reactor pressure vessel simulated by an atomic reactor characteristic analysis section 13 is subject to animation processing by an animation operating section 23 and the result is displayed on an animation display section 25. Thus, the transition of phenomenon with respect to the thermo hydraulic behavior in the inside of the atomic reactor pressure vessel is recognized directly visually to the trainees. As a result, the understanding of the trainees to events, especially the understanding with respect to the thermo hydraulic behavior in the atomic reactor pressure vessel is improved and the effect of training is improved remarkably.
    • 7. 发明专利
    • COMMUNICATION SUPPORT SYSTEM
    • JPH06117885A
    • 1994-04-28
    • JP837191
    • 1991-01-28
    • TOSHIBA CORP
    • SUMIYAMA SHIGEAKISUZUKI KENICHIKATO MASAMI
    • G01D21/00G21D3/04
    • PURPOSE:To decide an appropriate solution when abnormality occurs in a nuclear plant which is a gigantic system by effectively exchanging the intellectual knowledge of each engineer among the engineers. CONSTITUTION:When the supplying flow rate of water becomes abnormal, a function analyzing system take a countermeasure against the abnormality, but, when the identification of the fault is impossible, the title system 30 is actuated. Then a data base 32 for a communication member list establishes 31 and 33 an initial community with already set members in accordance with the abnormal plant event. The members are connected to each other through a distributed network and information exchange is performed among the members in accordance with a hyper-text by means of an information exchange monitoring function 34 and the final decision is made 35. The final decision is displayed together with the degree of confidence of the members. When the degree of confidence is smaller than a set value, another community larger than the initial community is established by calling a specialist group and the members are asked to discuss until the degree of confidence of the members becomes larger than the set value. The decided cause, countermeasure, etc., of the event are immediately transmitted to operators so as to cope with the plant abnormality.
    • 8. 发明专利
    • INHERENT SAFETY NUCLEAR REACTOR
    • JPH01101497A
    • 1989-04-19
    • JP25822487
    • 1987-10-15
    • NIPPON ATOMIC IND GROUP COTOSHIBA CORP
    • SUMIYAMA SHIGEAKI
    • G21C7/30G21C3/06G21C3/28G21C9/00
    • PURPOSE:To suppress reaction cleavage only when an abnormal event occurs and the temperature of a fuel rod rises by dividing the fuel rod lengthwise and connecting the respective divided fuel rod elements by joining members which expand and contract with temperature. CONSTITUTION:When a nuclear reactor is at the time of normal operation, the temperature of the fuel rod 13 is lower than a deformation point, so a bellows 31 is in a shrinkage state. At this time, the fuel rod 13 put in a fuel aggregate 11 is maintained at proper length to fission in the nuclear reactor. If an abnormal event occurs, the temperature of the sheath pipe 23 of the fuel rod 13 rises abruptly about 25sec after the occurrence of this abnormal event. At this time, the bellows 31 expands and the fuel rod 13 constituting the fuel aggregate 11 extends lengthwise. The fuel rod elements leave one another in the lengthwise direction and the coupling among neutron fields between those elements is weakened. This phenomenon is equivalent to a phenomenon obtained by putting a negative reaction degree in the reactor core.