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    • 1. 发明专利
    • NATURAL DRAFT COOLING DEVICE FOR DECAY HEAT REMOVAL
    • JPH032692A
    • 1991-01-09
    • JP13824989
    • 1989-05-31
    • TOSHIBA CORPCENTRAL RES INST ELECT
    • MATSUDA JUNKOKINOSHITA IZUMI
    • G21C9/00G21C15/12G21C15/18
    • PURPOSE:To improve a heat removal efficiency by arranging a heat collector which is formed by piling up continuously tubular materials of a predetermined length almost horizontally between a safety vessel and a concrete wall surrounding the safety vessel. CONSTITUTION:A heat collector 15 is formed by tubular materials of a regular polygon shape such as tubular materials 15a o a regular triangle shape, tubular material 15b of a square shape or tubular materials 15c of a regular hexagon shape, which are piled up continuously with keeping them horizontally, and also is formed so that a heat of a safety vessel 10 may be effectively transferred by a heat radiation when a decay heat is removed, and a heat may be effectively removed by a convection when an air from an outside passes through the heat collector 15 inside, as well. On the other hand, the air flowing in from the outside through an air inlet 8 goes down between a concrete wall 13 and the heat collector 15, is lead to an outside surface of the safety vessel through the inside, and is discharged to the outside from a stack 11. In this case, a geat heat transferring area can be obtained because the heat collector is an aggregation of tubular materials and therefore a surface of each material turns into heat transferring surface by the convection, and a heat removing capacity thereof is much increases.
    • 3. 发明专利
    • THERMAL SHIELDING DEVICE OF FAST BREEDER REACTOR
    • JPH01212396A
    • 1989-08-25
    • JP3519388
    • 1988-02-19
    • CENTRAL RES INST ELECTTOSHIBA CORP
    • KINOSHITA IZUMIYOKOSHIMA TOSHIAKI
    • G21C11/08G21C13/00
    • PURPOSE:To prevent the production of localized stress concentration by providing an inside partition for forming a gas dam space in the inner circumferential side of a reactor vessel and thermal shielding plates between an outside hanging shell and an inside hanging shell which are extended to the gas dam space. CONSTITUTION:A locking part 102 of an outside hanging shell 101 is formed on the upper end thereof and locked with a stage part 103 which is formed on a side circumferential wall 1a of a reactor vessel 1 from above. A shell part 104 is extended at the lower part of the locking part 102 and the lower end thereof is immersed in liquid sodium 3. A thermal shielding plate hanging part 105 is extended in the radial inside from the shell 104 of an upper position of a gas dam space 27 to projected and a plurality of thermal shielding plates 107 are hung on the hanging part 105 through a support member 106 and the lower end of these shielding plates 107 are immersed in the liquid sodium 32. An inner hanging shell 108 is attached to the inner circumferential end of the hanging part 105 and the lower end of the shell 108 is immersed in the sodium 32. Further, a cover 109 is attached to the upper part of the shell 108 and the inner circumferential end part of the cover 109 is immersed in a coolant 6.
    • 4. 发明专利
    • FAST BREEDER
    • JPH01210895A
    • 1989-08-24
    • JP3519188
    • 1988-02-19
    • CENTRAL RES INST ELECTTOSHIBA CORP
    • KINOSHITA IZUMINAKAMURA HIROSHI
    • G21C11/08G21C13/00
    • PURPOSE:To prevent local action of load, etc., and to maintain the soundness of a reactor vessel by improving the supporting structure for supporting plural heat shielding plates disposed within a gas dam layer formed on the inner circumferential side of the vessel. CONSTITUTION:The load of plural sheets of the heat shielding plates 30 is uniformly supported to a hanging plate 25 by means of supporting members 29 and is further supported by the reactor container 1. The horizontal load is uniformly transmitted to the adjacent shielding plates 30 via a projecting part 31 and is transmitted to the vessel 1 or an inner partition wall 21 when said load acts on the shielding plates 30 in the event of an earthquake. The load is thus prevented from acting locally on a specific part. The difference in thermal expansion by a temp. difference between the vessel 1 side and the partition wall 21 side is absorbed by the elastic deformation of the shielding plates 30. There are spacings 32 in the circumferential direction of the shielding plates 30 and there is the probability that the thermal shield function is impaired. However, the projecting parts 31 are in contact with the vessel 1 or the partition wall 21 or the shielding plates 30 and, therefore, natural convection is effectively suppressed and the thermal shield function is retained without being impaired.
    • 5. 发明专利
    • DOUBLE TANK TYPE NUCLEAR REACTOR
    • JPH0659065A
    • 1994-03-04
    • JP21042892
    • 1992-08-06
    • CENTRAL RES INST ELECT
    • NISHIGUCHI YOHEIKINOSHITA IZUMI
    • G21C1/02
    • PURPOSE:To blowoff only gaseous components in a secondary container by constituting a cylindrical shell of a manometer seal in a structure with a large diameter part drooping to reach the inside of a double cylindrical tub from a roof slab and expanded upward in diameter. CONSTITUTION:When pressure inside of a secondary vessel 31 rises higher than set pressure, a blowoff system breakdown plate 58 is ruptured and gaseous reacting product materials such as H and others in the secondary vessel 31 pass a blowoff system piping 57 and are blown off to the air from an atmospheric blowoff part 61. The output port of the piping 57 is arranged adjacent to the inwall of a double cylindrical tub 34a of a manometer seal 34, that is, to the peripheral wall of the secondary vessel 31 and on the back face side of the secondary vessel 31. Additionally. on the upper part of a cylindrical shell 34b, a large diametrical part 34d is formed. Consequently, swirling flow components of a refrigerant (Na) in the secondary vessel 31 moving to the side of the manometer seal 34 are promoted and movement of Na to the inside of the piping 57 is restrained by a principle of centrifugation. Accordingly, only gaseous product materials flow in the piping 57, and flow of Na is prevented. Consequently, it becomes needless to provide a cyclone separator.
    • 6. 发明专利
    • DOUBLE TANK NUCLEAR REACTOR
    • JPH05107391A
    • 1993-04-27
    • JP27065991
    • 1991-10-18
    • CENTRAL RES INST ELECT
    • KINOSHITA IZUMINISHIGUCHI YOHEI
    • G21C1/02G21D1/00G21D1/02G21D3/04
    • PURPOSE:To avoid buckling of a primary container due to external pressure by connecting a communicating piping system between the cover gas spaces of secondary and primary containers, the piping system being provided with a failure plate which crushes at predetermined pressure and a check valve which allows gas flow only from secondary to primary side. CONSTITUTION:A cover gas space is formed on a secondary high temperature pool 49 in a secondary container 31 and a primary container 35 is provided within the container 31 and a cover gas space is formed also on a primary high temperature pool 39 in the container 35. A communicating piping system 68 is provided which connects the cover gas spaces of the containers 31, 35 together via a roof slab 33 and which comprises a failure plate 64, a check valve 65 being open from a secondary system to a primary system, primary and secondary stop valves 66, 67, and piping 64. When the container 35 is 10m in diameter, 12m in the length of its cylindrical portion, 50mm in plate thickness and at a temperature of 500 deg.C, for example, the rule of thumb relating to buckling under external pressure is a differential pressure of about 5kg/cm . When the set pressure of the failure plate 63 to deal with sodium- water reaction accidents is about 4kg/cm , buckling of the container 35 due to external pressure can be prevented.
    • 8. 发明专利
    • DIRECT CONTACT HEAT TRANSFER TYPE STEAM GENERATOR
    • JP2000009887A
    • 2000-01-14
    • JP17364598
    • 1998-06-19
    • CENTRAL RES INST ELECT
    • NISHI YOSHIHISAKINOSHITA IZUMIFURUYA MASAHIRO
    • G21D1/00
    • PROBLEM TO BE SOLVED: To obtain a superheated steam superior in steam conditions by facilitating superheating generated saturated steam. SOLUTION: This steam generator 27 is provided with a vessel 29 in which a primary cooling system piping 28, wherein liquid sodium having passed a core and became a high temperature flows, passes from the top to the bottom, a secondary coolant 30 stored in the vessel and heated by the heat of liquid sodium, a water injection nozzle 6 directly injecting water into the secondary coolant 30, a steam generation part 3 generating steam by direct contact heat transfer between the secondary coolant 30 and the water injected from the injection nozzle 6 in it, a superheated steam generation part 31 exchanging heat between the separated steam from the secondary coolant 30 and the primary coolant flowing through the primary cooling system piping 28 and a steam outlet 7 provided at the upper part of the vessel 29. Steam is generated by the direct contact heat transfer between the secondary coolant 30 heated by the primary coolant in the steam generator 34 and water, and this steam or slightly superheated steam is superheated by the high temperature primary coolant flowing in the primary cooling system piping 28 during rising in the space in the superheated steam generator 31 so that superheated steam superior in steam conditions is obtained.
    • 9. 发明专利
    • DOUBLE TANK TYPE REACTOR
    • JPH07167978A
    • 1995-07-04
    • JP31479893
    • 1993-12-15
    • CENTRAL RES INST ELECT
    • NISHIGUCHI YOHEIKINOSHITA IZUMIYOSHIDA KAZUO
    • G21C13/024
    • PURPOSE:To provide a double tank type reactor lightweight, simple in structure and high in reliability with a simple reactor storage facilities. CONSTITUTION:A secondary vessel 3 is supported by the side wall part 4a of a reactor supporting structure 4, and a primary vessel 2 is suspended on the inside of the secondary vessel 3 from a secondary roof slab 7 at the upper part of the reactor supporting structure 4. A core 19 is installed at the bottom part of the primary vessel 2, and a core upper instrumentation device 25 and a control rod driver 24 are provided above the core 19. Plural primary cooling material electromagnetic pumps 14 and intermediate heat exchangers 15 are disposed around the control rod driver 24, and plural secondary cooling material electromagnetic pumps 27 and steam generators 28 are disposed between the primary vessel 2 and the secondary vessel 3. The side wall part of the secondary vessel 3 is supported by supporting members 6 extended from the reactor supporting structure 4. The side wall upper end part outer periphery of the secondary vessel 3 is provided with a manometer seal tub 8. Solder 10 is filled into the bottom part of the manometer seal tub 8, and the lower end part of a manometer seal cylindrical drum 9 extended from the secondary roof slab 7 is inserted therein.
    • 10. 发明专利
    • METHOD FOR CONSTRUCTING NUCLEAR POWER PLANT REACTOR
    • JPH05107381A
    • 1993-04-27
    • JP27066091
    • 1991-10-18
    • CENTRAL RES INST ELECT
    • KINOSHITA IZUMISATO MORIHIKO
    • E04G21/14E04H5/02G21C13/00
    • PURPOSE:To shorten the construction period of a prefabricated nuclear power plant by omitting the field erection of the plant. CONSTITUTION:The outer peripheral area of a reactor container is partitioned into several units on a nuclear reactor building base mat 11 and steel boxes in which equipment, piping and electric components to be disposed in each unit are stored are fabricated as first to sixth unit modules 1-6 in a factory. The unit modules 1-6 are installed on the nuclear reactor building base mat 11 at a construction site. The boxes facing the reactor container are joined together and the reactor container is covered at its upper side with confinement modules 7-9 and the confinement modules 7-9 are placed on the box walls of the unit modules 1-6 and joined together. During the process of installing the unit modules 1-6 a nuclear reaction module 12 with which the reactor container and a reactor core main body are fabricated integrally is installed on the nuclear reactor building base mat 11. The unit modules 1-6, the confinement modules 7-9, and the nuclear reactor module 12 are installed on the nuclear reactor building base mat 11 and are joined together and then the work of connecting piping and electrical wiring among the modules is performed.