• 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 device for transversely restraining the fuel rods of a bundle of fuel rods for a nuclear reactor assembly comprises an upper grid, a lower grid and an intermediate grid arranged in the direction of the axes of the fuel rods, each grid defining cells through which the fuel rods extend, the upper and lower grids being identical and made integral, and the intermediate grid being made of resilient material and arranged with its cells staggered transversely relative to those of the upper and lower grids so that the walls of the cells of the intermediate grid press the rods against the walls of the cells of the upper and lower grids.
    公开号:SU884591A3
    申请号:SU792763346
    申请日:1979-05-14
    公开日:1981-11-23
    发明作者:Леклерк Жозеф
    申请人:Фраматом (Фирма)；
    IPC主号:
    专利说明:

    The invention relates to nuclear technology, and in particular to devices for laterally holding fuel rods in the fuel assembly of a nuclear reactor. δ
    A known design of the spacer of a nuclear reactor lattice, including spacer elements in the form of strips mounted on the rim of the lattice and restricting the transverse movement of fuel elements (TVEL) in the assembly [1].
    The disadvantage of such a lattice is the low reliability of the ordered retention of fuel elements due to the significant hydro-15 dynamic effects of the coolant flow.
    A spacer grid of a nuclear reactor is also known, comprising a device for spacing the top 20 beer rods in a fuel assembly of a nuclear reactor, including transverse spacing elements of metal plates assembled in the form of a grid with square cells through which 25 fuel rods pass. Direct spacing of the fuel rods is carried out using profiled spring elements installed in the grill separately for each rod f2j.
    The disadvantage of this lattice is to reduce the reliability of the structure due to the difficulty of ensuring a constant lateral force acting on each of the rods located in the beam, since the bent plates are made and installed separately.
    The purpose of the invention is to increase the operational reliability of the lattice by reducing the vibration of the fuel rods in the lattice.
    This goal is achieved by the fact that the device for spacing fuel rods in the fuel assembly of a nuclear reactor, including transverse spacing elements from metal plates assembled in the form of a grid with square cells, through s 88459!
    which the fuel rods pass, is made of three gratings located on each other along the height of the assembly, the two extremes of which are equal, and the middle located between 5 of them is made of elastic metal plates whose height is less than the height of the extreme gratings and is installed with an offset of transverse direction relative to the vertical axis of the extreme lattices and is in contact with fuel cells resting on the cell walls of the extreme lattices.
    On the extreme lattice, rectangular cutouts are made, in which the 15 middle lattice is installed.
    The middle lattice has two axes of symmetry, limiting the parts of the lattice with lateral movement, symmetric displacements in other parts of the lattice 2 θ relative to the axes of the lattice.
    In addition, the middle grate is composed of a set of gratings located on top of each other over the entire height of the fuel cells. 25
    At the edges of the metal plates of the middle lattice, deflectors are made for guiding the rods when they are installed.
    The plates of the middle lattice are made of a material with a large coefficient of 3 θ linear expansion with respect to the material of the plates of the extreme lattices.
    In FIG. 1 shows several grid cells, general view; in FIG. 2 one of the cells with a fuel cell, top view; in FIG. 3 - 35 embodiment performed neniya device comprising four identical sectors, top view; in FIG. 4 and 5 - cell options, general view.
    The device contains identical upper 1 and lower 2 parts, consisting of lattices with square cells 3, as well as the middle part in the form of a lattice with square cells 5 of the same size but smaller lattice height, 45 than the upper 1 and lower 2 lattices. ''
    The gratings 1 and 2 are fixed with their lateral edges on the metal plate 6 while maintaining a certain longitudinal gap between the gratings and 50 consist of metal plates 7 rigidly assembled perpendicular to each other.
    All three lattices form a single design of the spacer device 55 for the transverse holding of the fuel rods. The sizes of the cells correspond to the sizes of the fuel rods passed through them, as well as the support pipes of the set of rods installed instead of some fuel cells.
    Metal plates made of a material with a small neutron absorption cross section, for example, zirconium alloy, are connected by welding to obtain a rigid lattice with the possibility of more accurate dimensional compliance to ensure proper spacing of fuel cells inside the beam.
    t
    The middle lattice 4 also consists of metal plates assembled along identical lattices 1 and 2 of the grid.
    Cutouts 8 are made in the plates 7, which make it possible to place the middle lattice 4 so that it is somewhat offset in the transverse direction relative to the lattices 1 and 2.
    The fuel rod 9 is installed inside the cell 3 and is held in position by the walls 10 of the middle grill 4 in contact with the surface of the fuel rod 8, which also rests on the plates of the upper grill 1.
    The walls 10 of the middle lattice are elastic, which makes it possible to act on the fuel rod 9 when the middle lattice 4 is offset by a certain amount in the transverse direction relative to the axis of the upper 1 and lower 2 lattices.
    The middle lattice 1 is made of a material whose elasticity is well preserved under irradiation conditions, for example, from an inconel material.
    In FIG. 3 shows an embodiment of the device in which the middle lattice 4 is divided into four sectors bounded by the symmetry axes of this lattice. Each of the sectors is limited inward by 4 binary walls of metal plates welded together. In each of the sectors, the displacements are symmetrical about the axis of symmetry of the lattice 4. The advantage of this embodiment is the balancing of the forces acting on the fuel elements 9 from the lattice 4, which is movable relative to the upper 1 and lower 2 lattices within the gap due to the presence of cutouts 8.
    On the walls of the cell can be made rigid protrusions IJ. located on the same vertical (Fig. 4).
    On the middle grill 4, small inclined deflectors 12 are made, which allow for the installation of the fuel element 8 in the cell.
    The implementation of the upper 1 and lower 2 lattices of a material that differs in the coefficient of linear expansion from the material of the middle lattice 4, allows for an increase in clamping force during assembly operation at operating temperatures.
    The middle lattice 4 is installed with an offset relative to the lattices 1 and 2 and, due to the elasticity of the plates from which it is made, allows the fuel elements 8 to be affected by a transverse force, which can be adjusted depending on the offset of the lattice 4.
    The proposed device allows to obtain a controlled transverse contact force between the fuel elements of the assembly and the spacing device, which makes it possible to reduce the vibration of the fuel rods in the assembly.
    权利要求:
    Claims (2)
    [1]
    38, which the fuel rods pass, is made of three gratings arranged one above the other along the height of the assembly, the two extreme of which are equal, and the middle one between them is made of elastic metal plates whose height is less than the height of the extreme gratings and installed with an offset in the transverse direction relative to the vertical axis of the extreme grids and is in contact with the fuel cells, resting on the walls of the cells of the extreme grids. At the extreme lattice, right-angle cuts are made in which the middle lattice is installed. The middle lattice has two axes of symmetry, limiting the portions of the lattice with transverse displacement, symmetrical displacements in other parts of the lattice relative to the axis of the lattice. In addition, the average lattice composition of Lena from a set of lattices located on top of each other over the entire height of the fuel cells. Deflectors are made on the edges of the metal plates of the lattice to guide the rods during their installation. The plates of the middle lattice are made of a material with a large linear expansion coefficient relative to the material of the plates of the extreme lattices. FIG. 1 shows several lattice cells, a general view; in fig. 2 one of the cells with a fuel cell, top view; in fig. 3 shows an embodiment of a device comprising four identical sectors, top view; in fig. 4 and 5 - variants of whose ki, a general view. The device contains identical upper 1 and lower 2 parts consisting of gratings with square cells 3, as well as a middle part in the form of a grid 4 with square cells 5 of the same size, but a smaller height of the grid than the top 1 and bottom 2 grids. The lattices 1 and 2, with their lateral edges, are fixed on the metal plate 6 with preservation of a certain longitudinal gap between the lattices and consist of metal plates 7, rigidly assembled between each other perpendicularly to each other. All three grids form a single design of a spacer for transversely holding the heat-generating rods. The dimensions of the cells 5 correspond to the dimensions of the passed through nog togshivnyh rods, as well as the support tubes of a set of rods installed instead of some fuel cells. Metal plates made of a material with a small neutron absorption cross section, such as a circus alloy, are joined together by welding to form a rigid grid with more accurate dimensioning to ensure proper spacing of the fuel cells within the beam. The middle grating 4 also consists of metal plates assembled in a grid identical to the gratings 1 and 2. Cut-outs 8 are made in the plates 7, allowing to place the middle grating 4 so that it is slightly displaced in the transverse direction relative to the gratings 1 and 2.. . The fuel rod 9 is installed inside the cell 3 and held in position by the walls O of the middle grid 4, which are in contact with the surface of the fuel rod 8, which also rests on the plates of the upper grid 1. The walls 10 of the middle grid are resilient, which makes it possible to act on the fuel rod 9 by force, when the middle grating 4 is displaced by a certain amount in the transverse direction relative to the axis of the upper 1 and lower 2 gratings. The middle lattice 1 is made of a material whose elasticity is well maintained under irradiation conditions, for example from inconel material. FIG. Figure 3 shows an embodiment of the device in which the middle grating 4 is divided into four sectors limited by the axes of symmetry of this grating. Each of the sectors is bounded in the direction to the inside of the lattice by 4 binary walls of metal plates welded to each other. In each of the displacement sectors, they are symmetric with respect to the axis of symmetry of the grid 4. The advantage of such an implementation is the balancing of the forces acting on the fuel cells 9 from the grid 4, which is movable relative to the upper 1 and lower 2 lattices within the gap due to the presence of notches 8. rigid protrusions II can be made. located on the same vertical (Fig. 4). On the middle grating 4, small inclined deflectors 12 are made, allowing installation of the fuel cell 8 into the cell. Making the upper 1 and lower 2 grids of a material differing in coefficient of linear expansion from the material of the middle grate 4 allows the clamping force to increase during operation of the assembly under conditions of operating temperatures. The middle grid 4 is set offset from the grids 1 and 2 and, due to the elasticity of the plates from which it is made, allows the transverse force 8 to act on the fuel cells 8, which can be adjusted depending on the shift of the grid 4. The proposed device allows obtaining a controlled transverse the contact force between the fuel cell assemblies and the remote controller, which makes it possible to reduce the vibration of the fuel rods in the assembly. Claim 1. Device for spacing fuel rods in a fuel assembly of a nuclear reactor, including transverse spacer elements of metal plates assembled in a grid with square cells, through which fuel rods pass, characterized in that, in order to improve the operational reliability of the fuel assembly by reducing the possibility of vibration of the fuel rods in the grille, the device is made of three grids located one above the other along the height of 1 "assembly, the two outermost toryh are equal, and the average, between them, made of elastic metal plates which are lower than the outer set of grids and offset laterally relative to the vertical axis of the outer lattices and in contact with the fuel cells on the film opirayuschimis extreme cell arrays. 2. A device according to claim 1, characterized in that rectangular cuts are fitted on the extreme lattice, and the middle lattice is installed on it. 3. The device according to paragraphs. 1 and 2, characterized in that the middle lattice has two axes of symmetry, bounding the lattice parts with transverse displacement, symmetrical displacements in other portions of the lattice relative to the axes of the lattice. 4. Device on PP. 1-3, that is, that the middle lattice is composed of a set of lattices located on top of each other over the entire height of the fuel cells. 5. Device on PP. 1-4, characterized in that on the edges of the metal plates of the middle lattice there are deflectors for guiding the rods during their installation. 6. The device according to paragraphs. 1-5, characterized in that the plates of the middle lattice are made of a material with a large coefficient of linear expansion in relation to the material of the plates of the extreme lattices. Sources of information. Taken into account in the examination 1. A. Krapepov A. Ya. Problems of nuclear reactor design. M., Lomzdat, p. 203.
    [2]
    2. The patent of Germany No. 1764386, cl. G 21 C 3/34, published. 1976 (prototype).
    nn
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    FIG. four
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    KR960012039A|1996-04-20|Triangular lattice of a fuel unit that is a square of a hard water reactor
    同族专利:
    公开号 | 公开日
    DE2918112A1|1979-11-22|
    BR7903046A|1979-12-04|
    US4297170A|1981-10-27|
    IE48230B1|1984-11-14|
    JPS54152783A|1979-12-01|
    GB2022310B|1982-07-14|
    ES480693A1|1980-03-01|
    NL7903069A|1979-11-21|
    ZA792372B|1981-03-25|
    FR2426312A1|1979-12-14|
    GB2022310A|1979-12-12|
    SE431268B|1984-01-23|
    DE2918112C3|1982-04-01|
    DE2918112B2|1981-07-09|
    BE876368A|1979-11-19|
    IE790943L|1979-11-19|
    JPS5933863B2|1984-08-18|
    PT69521A|1979-05-01|
    IT1118608B|1986-03-03|
    IT7967990D0|1979-05-10|
    SE7904157L|1979-11-20|
    FR2426312B1|1982-04-30|
    引用文献:
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    DE4118124A1|1991-06-03|1992-12-10|Siemens Ag|FUEL ELEMENT WITH A GRID STRUCTURE BETWEEN THE RODS|
    US5365557A|1992-06-10|1994-11-15|Siemens Aktiengesellschaft|Fuel assembly of a nuclear reactor with a grid structure for producing spin|
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    GB1126733A|1964-12-23|1968-09-11|Atomic Energy Authority Uk|Locating structure|
    FR1483433A|1965-06-16|1967-06-02|Atomic Energy Commission|Assembly device for fuel element rods for nuclear reactors|
    DE1514559A1|1965-09-03|1969-06-26|Siemens Ag|Spacer for nuclear reactor fuel elements|
    GB1198151A|1967-05-15|1970-07-08|Atomic Energy Authority Uk|Nuclear reactor Fuel Element Assemblies|
    US3933583A|1968-11-07|1976-01-20|The Babcock & Wilcox Company|Nuclear fuel rod frame with fuel rods positioned by moveable member|
    US3715275A|1970-03-02|1973-02-06|Combustion Eng|Bimetallic spacer grid arrangement|
    DE2012787A1|1970-03-18|1971-10-07|Licentia Gmbh|Mounting spacers for nuclear fuel rods|
    BE785941A|1971-07-07|1973-01-08|Atomic Energy Authority Uk|IMPROVEMENTS IN THE FUEL ELEMENTS OF NUCLEAR REACTORS|
    BE785940A|1971-07-07|1973-01-08|Atomic Energy Authority Uk|IMPROVEMENTS IN THE FUEL ELEMENTS OF NUCLEAR REACTORS|
    BE785942A|1971-07-07|1973-01-08|Atomic Energy Authority Uk|IMPROVEMENTS IN THE FUEL ELEMENTS OF NUCLEAR REACTORS|
    US3982994A|1975-02-24|1976-09-28|The Babcock & Wilcox Company|Grid lattice with horizontally-movable bar|
    US4039379A|1975-02-28|1977-08-02|Exxon Nuclear Company, Inc.|Mixing vane grid spacer|US4389369A|1980-08-11|1983-06-21|Westinghouse Electric Corp.|Bi-metallic grid for a nuclear reactor fuel assembly|
    FR2514932B1|1981-10-16|1986-11-14|Commissariat Energie Atomique|SPACING GRILLE FOR NUCLEAR REACTOR FUEL ELEMENT|
    FR2594998B1|1986-02-24|1988-06-10|Fragema Framatome & Cogema|GRILLE FOR NUCLEAR FUEL ASSEMBLY, AND ASSEMBLY COMPRISING APPLICATION|
    JPH0559397B2|1987-04-30|1993-08-30|Mitsubishi Genshi Nenryo Kk|
    US4818471A|1987-08-10|1989-04-04|Westinghouse Electric Corp.|BWR fuel assembly channel with localized neutron absorber strips for LPRM calibration|
    JPH0797152B2|1988-11-16|1995-10-18|三菱原子燃料株式会社|Nuclear fuel assembly and assembling method thereof|
    US5188798A|1988-11-16|1993-02-23|Mitsubishi Nuclear Fuel Co.|Grid for nuclear fuel assembly|
    FR2662010B1|1990-05-10|1992-08-21|Framatome Sa|GRID FOR NETWORK NUCLEAR FUEL ASSEMBLY AND ASSEMBLY INCLUDING APPLICATION.|
    SE469299B|1991-10-29|1993-06-14|Asea Atom Ab|DISTRIBUTOR FOR CONTAINING BRAINSLET STARS IN A CORE REACTOR'S BRAINSLE PATTERN|
    US5178825A|1991-11-29|1993-01-12|General Electric Company|Fuel bundle and spacer utilizing tapered fuel rods|
    US5375154A|1993-04-15|1994-12-20|General Electric Company|Reduced pressure drop spacer for boiling water reactor fuel bundles|
    US5434898A|1994-03-14|1995-07-18|Siemens Power Corporation|Nuclear fuel assembly|
    FR2764427B1|1997-06-05|1999-08-20|Atea|RACK FOR STORING NUCLEAR FUEL ASSEMBLIES AND MANUFACTURING METHOD THEREOF|
    ES2216356T3|1998-01-27|2004-10-16|Framatome Anp Gmbh|SPACER OF A FUEL ELEMENT OF A NUCLEAR POWER PLANT.|
    DE29801286U1|1998-01-27|1998-04-23|Siemens Ag|Spacer for a fuel element in a nuclear power plant|
    US6519309B1|2000-06-29|2003-02-11|Framatone Anp Inc.|Pressurized water reactor fuel assembly spacer grid|
    FR2923321B1|2007-11-05|2009-12-18|Areva Np|NUCLEAR FUEL PEN HOLDING GRID, AND FRAME AND ASSEMBLY COMPRISING SUCH A GRID.|
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    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    FR7814860A|FR2426312B1|1978-05-19|1978-05-19|
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