• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    1. SUPPORT DEVICE FOR. FASTENINGS OF THE HEAT-CARRIER CIRCULATION SYSTEM formed by the hull; nuclear reactor and at least two vertical steam generators, located symmetrically around the reactor, each of which is abraded to the reactor pipeline, whose length is commensurate with its diameter ,. including supporting structure with supporting bearings, which is so that, in order to increase the reliability of the systems by increasing the rigidity of the mounting of its elements, each supporting bearing of the reactor and steam generators is made in the form of corresponding to the V - shaped groove of the surface of the support structure, about which, together, are the lower points of support, located c and more, but in the same horizontal plane. at the same time, each steam generator has a bearing on the opposite side of the reactor, and in the lower frame of the supporting structure there are concentric polygonal shells installed around the perimeter of the nuclear reactor and fixed at the bottom on the thick-walled circular plate, and at the top - on a horizontal intermediate plate. 2. The device according to claim 1, in which the lateral chambers are made in the upper part of the supporting structure, in the upper wall of each of which a bearing is installed with a cluster located inside it fixed vertically to the upper end of the steam generator; interconnected by means of box-shaped rigid elements, and the inner walls of the chambers are the walls of the pool of unloading of fuel elements located 1 1 between the side chambers above the CO 3- reactor. The device according to claims. 1 and 2, ate is different from the fact that inside each chamber its lower part is. These are horizontal stops, located in the longitudinal vertical plane on opposite sides of each of the steam generators. 4. The device according to PP. 1-3, each of which has a support; On the trunnion attached to the housing, there is an axial through hole for the passage of the pipeline.
    公开号:SU1036256A3
    申请号:SU792784923
    申请日:1979-06-22
    公开日:1983-08-15
    发明作者:Пьерар Робер
    申请人:Ателье Э Шантье Де Бретань Ацб (Фирма)；
    IPC主号:
    专利说明:

    The invention relates to atomic technology, in particular to devices for rigid attachment of a nuclear reactor vessel connected to steam generators to form a first control reactor reactor. The design of the support system is known, which includes metal spacial structures that enclose the element of the circulation circuit of the heat carrier of the steam generator. Such a system allows the structural elements to have some possibility of moving relative to each other fl. The disadvantage of this implementation is the possibility of mutual displacement of structural elements, which reduces the reliability of the entire installation. Closest to the present invention is a support device for cracking the circulating coolant system formed by a shell-sod reactor and at least two vertical steam generators arranged symmetrically around the reactor, each of which is connected to a reactor piping whose length is commensurate with its diameter , including supporting structure with supporting bearings 2. The disadvantage of this design is in reducing the reliability of the systems due to low rigidity with independent mutual deformations and relative elongations. The purpose of the invention is to increase the reliability of the system by increasing the rigidity of its elements. The goal is achieved by the fact that in the support device for mounting the circulation system of the coolant formed by the core nuclear reactor and at least two vertical steam generators located symmetrically around the reactor, each of which is connected to the reactor by a pipeline, the length of which is commensurate with its diameter, including the supporting structure with supporting bearings, each supporting bearing of the reactor and steam generators is made in the form of a polygonal pin, located in corresponding V-shaped The groove of the surface of the supporting structure, together the lower points of support located symmetrically in one horizontal plane, each steam generator on the side opposite to the reactor having an hr bearing, and in the lower part of the supporting structure there are concentrically arranged polygonal shells covering the core perimeter of the reactor and fixed in the lower part on the annular thick-walled plate, and in the upper part - on the horizontal intermediate plate. In addition, in the upper part of the supporting structure there are side chambers, in the upper wall of each of which a bearing is installed with a pin inside it, secured: .. lined vertically on the upper end of the steam generator, while the chambers are interconnected by means of box-shaped rigid elements , and the entry walls of the chambers are the walls of the fuel cell discharge basin located between the side chambers above the reactor. Moreover, inside each chamber of its lower part there are horizontal stops, located in the longitudinal vertical plane on different sides of each of the steam generators, and each bearing pin fixed on the body has an axial through hole for the passage of the pipeline. FIG. 1 shows the proposed support structure and the steam generator housing system, a longitudinal section in FIG. 2 shows section A-A in FIG. G; in fig. 3 - section BB in FIG. one; in fig. 4 shows a section B-B in FIG. one; in fig. 5 - speaking. element welded to the body, cut (on an enlarged scale); in fig. 6 - protruding element, cross-section. The device comprises a reactor case 1 connected to two steam generators 2 using very short pipes 3, as well as primary circulation pumps 4, which are fixed under the water by the jackets 5 of steam generators 2. Axes 6 and 7 of case 1 and steam generators 2 are located in one plane, which is longitudinal. The power structure consists of two very rigid metal structures, namely the lower and upper, rigidly connected by corresponding connecting devices to each other and along the interface plane that has the partition. The lower structure consists of two coaxial shells - 8 inner and 8 outer, as well as lateral extension 10, covering water shirts 5 of steam generators 2. Shells 8 and 9, surrounding housing 1, are welded to the slab with their base. Of thick sheet material and form between by itself and with the housing 1 sealed volumes or caissons 11, which are filled with water to provide the required neutron protection. Coaxial shells 8 and 9 are shaped like a polyhedron. Shell 8 is formed by joining thick sheets to form a rectangular parallelepiped, which is surrounded by a shell 9, having the shape of a straight prism, with an irregular eight in the base, also formed by thick sheets. The prismatic sheath 9 has lateral protrusions 10 on each side in the upper part for covering and securing the lower part of the steam generators 2 (Fig. 1). . The housing 1 and the generators 2 are supported on the lower structure 5 by means of protruding elements 12 and 13, respectively, of the reactor and the steam generator having the form of trunnions. The protruding elements 12 are welded on the side of the housing so that their common axis is perpendicular to the common axis of the protruding elements 13, attached to the side in the lower part on the steam generators 2. The protruding elements 12 are mounted sliding in self-aligning bearings 14, the protruding element 13 of each steam generator 2 is also mounted with a slide in a self-aligning bearing 15 provided in the lateral projection 10 of the lower structure. The protruding elements 12 and-13, welded on the housing 1 and the steam generators 2, have a cross section. a polygon shape that fits in self-aligning bearings with a corresponding multi-angle hole so as to maintain a strictly fixed extended plane passing through axes 6 and 7 in the case of transverse and longitudinal movements and allows for expansion of the system fixed by sliding supports of protruding elements . Elements 12. and 13 may have a square shape in cross section, such as a hole in the corresponding bearings, so that one of the diagonal square is directed. vertically, and the other horizontally. Thus, the support keeps the steam generator case in a strictly fixed system in a single power structure. If the protruding elements 12 ″ 1 have a regular octagon in cross section, then the bearings 14 and 15 also have corresponding octagonal holes. The upper structure is formed by joining thick sheets so as to create in its central part the walls of the fluid basin 16 of the reactor body 1, as well as two straight prisms with a trapezoidal base, forming a shell around two boregenerators, with a large base of the trapezium forming one of the walls of the unloading basin. In the upper part, stiffening elements 18 are located, connecting two prisms 17. Each steam generator 2 has a protruding element 19 at the upper end or apex, which is welded to the steam generator and is a bearing of this type, such as elements 12 and 13. Elemen a square cross section is mounted by sliding in a self-mounting bearing with a rectangular bore located at the top of the upper structure and located on the axis of the steam generator 2. Like the supporting elements 12 and 13, the elements 19 are engaged in blocking housing and generators, most of the generators in the transverse direction in case of impact or rupture of the pipe 3 of the system housing 1 - steam generator 2. In the lower part of each generator 2 there are two diametrically opposed bilge devices that do not prevent expansion. The device 20, located on the side of the protruding element 13, is stationary and 1 blocking the steam generator in the longitudinal direction in the event of a cut connection, and the device 21, located on the side of the housing 1, blocks the generator in the transverse direction in TaikoM. In construction, it is possible to create a gap between the end of each protruding element 12 by the safety buffer 22, which prevents the housing from shifting along the axis of the elements 12 in the event of a rupture of the connections 3 between the case and generators. The protruding elements 12, welded to the housing 1, have an internal opening 23, which makes it easy .KOH-J to roll the weld 24 on the housing 1, and also allows the discharge pipelines (not shown) to be passed along the axis of the hole. Thus, the system of the upper and lower structures provides a very rigid and with very high mechanical strength fastening of the elements of the primary circuit of the nuclear reactor, being an effective biological protection and providing a fixed and precise arrangement of the constituent elements in all planes. In addition, the housing system — a steam generator — is not subjected to extreme stresses due to the flexibility of communication through the housing — a geogram.
    权利要求:
    Claims (4)
    [1]
    (54) 1. SUPPORT DEVICE 'FOR. FASTENERS OF THE HEATING CIRCULATION SYSTEM formed by the case; .....
    a nuclear reactor and at least two vertical steam generators located symmetrically around the reactor, each of which is connected to the reactor by a pipeline, the length of which is comparable with its diameter, including a support structure with support bearings, and so on that, in order to increase the reliability of the system by increasing the rigidity of the fastening of its elements, each thrust bearing of the reactor and steam generators is made in the form of a polygonal journal located in the corresponding V-shaped groove surface of the support structure, together forming the lower support points located symmetrically in the same horizontal plane. at the same time, each steam generator from the side opposite to the reactor has a support bearing, and in the lower part of the support structure there are concentric polygonal shells covering the perimeter of the nuclear reactor body and fixed in the lower part on an annular thick-walled plate, and in the upper part on a horizontal intermediate plate.
    [2]
    2. The device according to claim 1, characterized in that side chambers are made in the upper part of the supporting structure, in the upper wall of each of which there is a bearing with a pin located inside it, mounted vertically on the upper end of the steam generator, the chambers being connected between each other by means of box-shaped rigid elements, and the inner walls of the chambers are the walls of the fuel cell unloading pool, located
    Between the side chambers above the reactor
    [3]
    3. The device according to paragraphs. 1 and 2,
    It is characterized by the fact that inside each chamber its lower part is; These made horizontal stops located in a longitudinal vertical plane on opposite sides of each of the steam generators.
    [4]
    4. The device according to paragraphs. 1-3, characterized in that each support pin mounted on the housing has an axial through hole for the passage of the pipeline.
    类似技术:
    公开号 | 公开日 | 专利标题
    US3182002A|1965-05-04|Liquid cooled nuclear reactor with improved heat exchange arrangement
    EP2165339B1|2015-01-07|Nuclear reactor downcomer flow deflector
    US4064005A|1977-12-20|Device for supporting a nuclear boiler
    JP3056023B2|2000-06-26|Nuclear reactor, method of assembling the same, and reactor reflector
    SU1036256A3|1983-08-15|Support arrangement for supplying heat carrier circulation system
    US4859402A|1989-08-22|Bottom supported liquid metal nuclear reactor
    US7684535B2|2010-03-23|Reactor containment vessel
    US4309252A|1982-01-05|Nuclear reactor constructions
    US3293139A|1966-12-20|Prestressed concrete pressure vessel for nuclear reactors
    KR100300890B1|2001-10-22|Support for Reactor Pressure Tank
    US4645633A|1987-02-24|Double tank type fast breeder reactor
    US3355357A|1967-11-28|Prestressed concrete pressure vessels for use in nuclear installations
    US3488255A|1970-01-06|Thermal insulation structures and fast reactor having such insulation
    US4302296A|1981-11-24|Apparatus for insulating hot sodium in pool-type nuclear reactors
    US20200388409A1|2020-12-10|Component cooling water system for nuclear power plant
    US4233518A|1980-11-11|Fuel storage rack
    US4681731A|1987-07-21|Nuclear reactor construction with bottom supported reactor vessel
    US4909981A|1990-03-20|Nuclear reactor
    US4123325A|1978-10-31|Containers for housing nuclear reactors
    US4154651A|1979-05-15|Liquid metal cooled fast breeder nuclear reactors
    EP0162956A2|1985-12-04|Modular liquid metal nuclear reactor
    US4786462A|1988-11-22|Support structure for a nuclear reactor
    US4761261A|1988-08-02|Nuclear reactor
    US4949363A|1990-08-14|Bottom supported liquid metal nuclear reactor
    US4587081A|1986-05-06|Slab for closing the vessel of a fast neutron nuclear reactor
    同族专利:
    公开号 | 公开日
    DE2961956D1|1982-03-11|
    EP0012042B1|1982-01-27|
    US4511532A|1985-04-16|
    FR2434461B1|1982-11-26|
    CA1147871A|1983-06-07|
    ES481830A1|1980-08-16|
    EP0012042A1|1980-06-11|
    FR2434461A1|1980-03-21|
    AT626T|1982-02-15|
    JPS5517094A|1980-02-06|
    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    CA540455A|1957-05-07|Air-Way Industries|Vacuum cleaner filter bag safety device|
    FR3036E|1903-09-25|1904-08-12|Jacques Rebour|Cardan joint for motion transmission|
    FR335545A|1903-09-25|1904-01-29|Jacques Rebour|Cardan joint for motion transmission|
    DE840335C|1949-08-17|1952-06-05|Windenfabrik Gottfried Schober|Shaft coupling with a transmission part plugged into a sleeve of one shaft end|
    US2952019A|1956-05-07|1960-09-06|Schlumberger Well Sureying Cor|Methods and apparatus for investigating materials|
    GB889758A|1958-01-31|1962-02-21|English Electric Co Ltd|Improvements relating to nuclear reactors|
    NL121725C|1958-08-11|
    US3190807A|1960-09-07|1965-06-22|Combustion Eng|Pressure tube reactor|
    US3045724A|1960-10-07|1962-07-24|Mitchell Robert Irving|Circular saw guide and square attachment|
    US3254399A|1962-11-23|1966-06-07|Crawford Fitting Co|Bulkhead support and fastening means|
    US3264863A|1963-05-27|1966-08-09|Maropis Nicholas|Method and apparatus for detecting incipient boiling of a liquid|
    US3353875A|1964-07-27|1967-11-21|Maxwell R Karge|Linear motion bearing assembly|
    FR1440418A|1964-08-28|1966-05-27|Reactor Centrum Nederland|Support construction of a nuclear reactor|
    FR1489557A|1965-08-17|1967-07-21|Reactor Centrum Nederland|Reactor support allowing the expansion of the pipes that connect to it|
    US3454466A|1967-12-29|1969-07-08|Atomic Energy Commission|Nuclear reactor containment system for metropolitan sites|
    AT312112B|1970-06-23|1973-12-27|Waagner Biro Ag|Supporting structure|
    US3984282A|1970-08-05|1976-10-05|Nucledyne Engineering Corporation|Passive containment system for a nuclear reactor|
    US3659909A|1970-10-26|1972-05-02|James Egbert|Bearing constructions|
    US3716451A|1970-11-30|1973-02-13|Stone & Webster Eng Corp|Nuclear reactor power plant structural support system|
    US3937651A|1971-05-21|1976-02-10|Siemens Aktiengesellschaft|Nuclear reactor facility|
    BE792742A|1971-12-21|1973-06-14|Babcock & Wilcox Co|IMPROVEMENTS IN HEAT EXCHANGERS|
    US3771499A|1971-12-30|1973-11-13|Combustion Eng|Steam generator cradle support|
    FR2214938B1|1973-01-23|1976-05-14|Commissariat Energie Atomique|
    US3947322A|1973-05-25|1976-03-30|Siemens Aktiengesellschaft|Reactor pressure vessel support arrangement|
    US3916944A|1973-06-28|1975-11-04|Combustion Eng|Reactor vessel supported by flexure member|
    DE2341489C3|1973-08-16|1979-02-22|Siemens Ag, 1000 Berlin Und 8000 Muenchen|Nuclear reactor plant|
    AT336056B|1974-01-10|1977-04-12|Voest Ag|FLOATING BEARING FOR THE PIVOT OF A CONVERTER|
    FR2311388B1|1975-05-12|1977-12-09|Commissariat Energie Atomique|
    DE2706164A1|1977-02-14|1978-08-17|Kraftwerk Union Ag|ASSEMBLY UNIT CONSISTING OF COOLANT PUMP AND STEAM GENERATOR, PREFERABLY FOR BURST-PROOF NUCLEAR REACTOR SYSTEMS|
    US4115194A|1977-02-22|1978-09-19|The Babcock & Wilcox Company|Reactor pressure vessel support|FR2533064B2|1981-11-09|1986-05-16|Alsthom Atlantique|NUCLEAR PREMISES WITH BOILER AND EARTHQUAKE RESISTANT CONTAINER|
    FR2526572B1|1982-05-06|1988-04-15|Commissariat Energie Atomique|NUCLEAR BOILER SUPPORT DEVICE|
    US5152253A|1991-01-28|1992-10-06|Westinghouse Electric Corp.|Vessel structural support system|
    US5268944A|1992-06-24|1993-12-07|Westinghouse Electric Corp.|Nuclear reactor having a polyhedral primary shield and removable vessel insulation|
    WO2013163475A1|2012-04-25|2013-10-31|Holtec International, Inc.|Nuclear steam supply system|
    US9892806B2|2012-05-04|2018-02-13|Smr Inventec, Llc|Space saver flanged joint for a nuclear reactor vessel|
    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    FR7820405A|FR2434461B1|1978-06-23|1978-06-23|
    [返回顶部]