• 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:
    A nuclear reactor fuel assembly comprises a bundle of parallel rods which are transversely spaced by cross-pieces, and is supported by support tubes which extend between, and are fixed at their ends to, two grids. The grids have cells which are aligned with the fuel rods and through which the fuel rods can be withdrawn. The grids are detachably connected to end plates by sockets which are removably engaged in the end plates and cells of the grids.
    公开号:SU933005A3
    申请号:SU792762207
    申请日:1979-05-14
    公开日:1982-05-30
    发明作者:Леклерк Жозеф
    申请人:Фрашатом (Фирма)；
    IPC主号:
    专利说明:

    36330 The goal is achieved by the fact that B disassembles the assembly of fuel rods of a nuclear reactor, a pair of steam / shelch fuel rods, installed and assembled and equipped with river grids, support tubes, parts of the fuel rods located on the ground and reinforced in End parts with or with standard sleeves, (the cashe in the corresponding openings of the JHX terminal end, one end of the support tubes is fixed in the end grid, and the corresponding structure of the fuel rods is movably on the outer side with an end piece by means of a cylinder (cylindrical sleeves passing through the cells of the kosha lattice, while on the lower TOfne each is made square with a boom with its longitudinal movement through the cell of the end sieve C and square in the end plate , and at the upper end - an annular collar with a groove for turning and fixing the sleeve. At the same time, on the cylindrical part of the sleeve between the upper and lower flanges —Different clamps were made, position 1 opposite the holes in the end cap those. FIG. I shows the Hopta element for a nuclear reactor, side view; in fig. 2 shows section A-A in FIG. Ij in FIG. 3 - section BB in 4dag, 1 {fig. 4 mounting sleeve inside the hole in the upper hob and upper grille; in fig. 5 - the same, top view; in fig. 6 is a view of B in FIG. 4 | in fig. 7 mounting pilza position on the inner surface of the lattice. A set of nauseous cells contains a bundle of parallel fuel rods I, held in the form of a rigid bundle by means of transverse grids 2, arranged at approximately regular intervals along the length of the rods. End plates 3 are located in the upper and lower parts of the assembly. Inside the cells 4 of the grids 2 are fuel rods. Some of the cells 4 are occupied by support pipes 5, which close part of the fuel rods. The length of the support pipes 5 is slightly longer than the length of the fuel rods I. The pipes 5, with their ends, are combined in 55 13,
    Kshtsev lattices 6.
    Lattice 6 obryuvat network, consisting not kvashch) atnyh cells 7. Inside some
    end plate,
    权利要求:
    Claims (2)
    [1]
    In its lower part, the sleeve 10 also has a broad part in the form of 54 cells. 7 includes onofsibie pipes 5, ntxrro but fixed in this grid either by seaming or by seaming and welding. The end grill 6 consists of a series of metal tapes or plates 8 of a certain height, intersecting and fastened together. Some of the cells 9 of the grid 6 are designed for the passage of the mounting sleeves with the aim of assembling the K-type niw tah grid. The network formed by the lattices 7 of the lattice is located relative to the fuel rods of the set so that each of the glands 9, inside which there are no support pipes, is on the same vertical line with the PLI element 1. Thus, the network of the lattice 6 is located almost in the same way as shown in 4ig. 2. On the other hand, the size of the lattice cells 9 is such that the elements 1 can be made from BJKKaTb by longitudinal movement, passing them through the lattice cells. Thus, when one of the flange plates 3 is removed, the fuel elements of the kit can be removed, although the end grids 6 remain fixed in place on the support tubes 5. The rivet arms 6 are fixed on the end plates 3 by means of a cylindrical shape containing 10 the upper end of the annular flange 11, the lower surface of which forms the shoulder 12, which can come into contact with the bottom of the cavity 13 of circular cross section, made on the upper outer surface of the flange plate 3. When the end upper plate is installed on the plate then to set, its lower poverhnos1 contact with the upper surface of the grating 6 and the grooves 14 of the square section formed in the center of STI positive end plate 13 and extending through the slab through coincide with quad PATH 9 lattice cells. The dimensions of the cross sections of the holes 14 are the same as those of the cell 9. When the sleeve U is inside the groove 14 and the grid cell 9 (Fig. 4), its central part is cylindrical, round, the diameter of which is from the side of the grid cell somewhat reduced, inside the groove 14 and the cell 9, and the shoulder 12 rests on it a cavity made on the upper surface s of the collar 15 square cross section, which is slightly smaller than the cell size and the groove 14. During installation in place inside the end plate and the grid, to fix this The end plate relative to the grille, properly oriented sleeve 1O, can pass through groove 14, well 9, whose cross section and shape correspond to cross section of shoulder 15. Top shoulder 11 of the sleeve contains, on the other hand, slot 16, into which you can insert the screwdriver blade of the orientation sleeves in any direction by rotation. In this way, the sleeve can be positioned so that the liner of the collar 15 rests on the bottom surface of the grille (Fig. 6). When the sleeve 10 is inserted inside the end plate and the grill, it is fixed by applying pressure to the end plate and the inner surface of the sleeve, expanding the cylindrical part at the level of the groove 14 of the end plate, 0 into the corners of this groove (Fig. 7). Deformations 17 can be obtained inside the galaxy 1O by means of a razalzseki, i.e. by means of an elongated tool containing rollers at its end, defrosting metal sleeves. During the actual rot of this deformation, the extruded metal enters all four corners of the square groove 14 and thus blocks the liner from rotating relative to the end plate and the grate. This deformation also causes some shortening of the sleeve, which creates a pressing of the end pin to the grid by means of the supporting surfaces and contact with the upper part of the end plate and the lower part of the grid. The assembly consisting of supported tubes, spans, and grids connected to the ends of the support tubes retains some rigidity when one or both end plates are removed, then fuel cells can be removed or inserted into this design to replace them. or removal for control and testing. Thus, to fix the end plate on the corresponding grid, it is enough to install the end plate on the grid so that the grooves 14 coincide with the grid cells, and then insert the fixing sleeves 10 into these channels and orient them with a screwdriver. entered in the slot 16, and, finally, to carry out the deformation 18 inside the sleeves. Conversely, when it is desirable to dismantle the kit for removing defective elements® or elements intended for control or for which the kit is immersed in a pool, the reactor, the necessary operations are even simpler, they can be easily carried out at a distance complete set. To carry out the demilita- tion, it is sufficient to insert the blade of the screwdriver into the slots of 16 different sleeves located on the plate, and turn the sleeve with a screwdriver. The protrusions 17 formed in the sleeve at the time of assembly are formed by contact with the inner surface of the groove of square section 14, which causes the sleeve to unblock, allowing it to rotate and lower the clamping force between the end tube and the grille. After this, the seals can be easily removed from the cavities and the end plate can be removed. Claim 1. Disassembled assembly of fuel rods of a thrust reactor, containing parallel fuel rods installed in the assembly and spaced by transverse grids, supporting pipes, locally placed parts of the fuel rods and fixed in end parts by means of cylindrical sleeves located in corresponding openings x end parts, characterized in that, in order to reduce the time for dismantling the fuel rods, one end of the support tubes is fixed in an end grid having corresponding The cellular structure of the fuel rods and the outer part and the end part are movably connected by cylindrical sleeves passing through the end grid cells, while a square collar is made at the bottom end of each sleeve with the possibility of its longitudinal movement through the end grid cell and a square hole in the end plate, and on the upper end - an annular shoulder with a groove for turning and fixing the liner.
    [2]
    2. The removable assembly according to claim 1, characterized in that, on the cylindrical part of the sleeve, between the upper and lower burghamn vto / pyuny strains
    79330058
    There are clamps, located on the ngstep. Kramerov A. Ya. Questions of the design of openings in the xnitse slab. Of nuclear reactors. M., Atomie-Sources in Yurmatsin, 2. France french Ni 2368785,
    Schjny tju in attention at examination of 5 kl. With 21 With 3/32, published. 1979 (prototype)
    Tsag, 1971, p. 204, fig. 7.11.
    -3
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    . / 2- iHiif II I) nil ItIIIIII IIII II
    II II and t | II II II II II and II II II II
    4-4
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    FIG.
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    类似技术:
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    US3137635A|1964-06-16|Fuel elements for nuclear reactors
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    同族专利:
    公开号 | 公开日
    ES480692A1|1980-03-01|
    FR2426310A1|1979-12-14|
    IT7967939D0|1979-05-04|
    SE431267B|1984-01-23|
    IT1118619B|1986-03-03|
    ZA792371B|1981-03-25|
    IE48120B1|1984-10-03|
    DE2918052A1|1980-01-17|
    FR2426310B1|1982-03-19|
    IE790942L|1979-11-19|
    JPS5940280B2|1984-09-28|
    PT69520A|1979-05-01|
    BE876369A|1979-11-19|
    NL7903068A|1979-11-21|
    GB2021303B|1982-05-12|
    GB2021303A|1979-11-28|
    DE2918052C2|1983-06-30|
    JPS54152782A|1979-12-01|
    BR7903081A|1979-12-04|
    SE7904156L|1979-11-21|
    US4302294A|1981-11-24|
    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    DE4214371A1|1992-04-30|1993-11-04|Siemens Ag|FUEL ELEMENT WITH DISPLACEMENT BODIES|BE625489A|1961-12-01|
    GB1148881A|1965-05-13|1969-04-16|Atomic Energy Authority Uk|Improvements in or relating to fuel assemblies for nuclear reactors|
    FR1536257A|1966-05-25|1968-08-16|Westinghouse Electric Corp|Fuel assemblies for nuclear reactors|
    US3791466A|1969-05-19|1974-02-12|Westinghouse Electric Corp|Low parasitic capture fuel assembly structure|
    BE759403A|1969-11-26|1971-04-30|Babcock & Wilcox Co|PERFECTED FUEL ASSEMBLY FOR A NUCLEAR REACTOR|
    CA941077A|1971-01-21|1974-01-29|Joseph R. Weiss|Nuclear fuel element with multiple fuel tubes|
    US3920516A|1972-09-25|1975-11-18|Westinghouse Electric Corp|Nuclear reactor fuel assembly arrangement|
    US3992259A|1973-06-25|1976-11-16|Combustion Engineering, Inc.|Fuel assembly for a nuclear reactor|
    US3971575A|1974-11-29|1976-07-27|Combustion Engineering, Inc.|Releasable locking device|
    US4135972A|1976-03-29|1979-01-23|Combustion Engineering, Inc.|Nuclear reactor spacer assembly|
    US4081324A|1976-06-17|1978-03-28|Exxon Nuclear Company Inc.|Spacer capture rod to spacer grid attachment device|
    FR2368785B1|1976-10-20|1980-08-08|Framatome Sa|US4535523A|1981-03-11|1985-08-20|Commissariat A L'energie Atomique|Fuel assemblies for nuclear reactors|
    FR2479536B1|1980-03-26|1983-09-16|Commissariat Energie Atomique|
    ZA815600B|1980-09-12|1982-08-25|Westinghouse Electric Corp|Reconstitutable fuel assembly for a nuclear reactor|
    FR2491668B1|1980-10-08|1985-10-11|Framatome Sa|NUCLEAR REACTOR FUEL ASSEMBLY|
    FR2514188B1|1981-10-05|1985-08-16|Framatome Sa|FUEL ASSEMBLY FOR A NUCLEAR REACTOR|
    US4684495A|1984-11-16|1987-08-04|Westinghouse Electric Corp.|Fuel assembly bottom nozzle with integral debris trap|
    US4716016A|1985-03-04|1987-12-29|Westinghouse Electric Corp.|Universal fuel assembly construction for a nuclear reactor|
    US4818473A|1985-05-08|1989-04-04|Westinghouse Electric Corp.|Fuel bundle|
    US4683117A|1985-09-09|1987-07-28|Westinghouse Electric Corp.|Nuclear fuel assembly incorporating primary and secondary structural support members|
    US4820475A|1985-09-12|1989-04-11|Westinghouse Electric Corp.|Burnable absorber rod push out attachment joint|
    US4683108A|1985-12-10|1987-07-28|Westinghouse Electric Corp.|Locking screw apparatus and method for underwater remote replacement|
    US4751042A|1986-02-18|1988-06-14|The Babcock & Wilcox Company|Removable control rod drive shaft guide|
    DE4117623A1|1991-05-29|1993-02-18|Siemens Ag|Fuel element esp. for thermal reactor - has sub-elements with reversible identical end plates which are rigidly connected by elongate tie-rods to fix end-plate spacing|
    FR2677163B1|1991-05-30|1994-01-07|Framatome|THERMOHYDRAULIC GRILLE AND NUCLEAR FUEL ASSEMBLY INCLUDING APPLICATION.|
    AU2003293927A1|2002-08-08|2004-03-19|Framatome Anp Gmbh|Fuel element for a pressurized water nuclear reactor|
    DE10236400B4|2002-06-29|2005-08-18|Framatome Anp Gmbh|Fuel element for a pressurized water nuclear reactor|
    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    FR7814859A|FR2426310B1|1978-05-19|1978-05-19|
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