WO2018021044A1 - Boiling-water reactor reactor-core - Google Patents

Boiling-water reactor reactor-core Download PDF

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Publication number
WO2018021044A1
WO2018021044A1 PCT/JP2017/025514 JP2017025514W WO2018021044A1 WO 2018021044 A1 WO2018021044 A1 WO 2018021044A1 JP 2017025514 W JP2017025514 W JP 2017025514W WO 2018021044 A1 WO2018021044 A1 WO 2018021044A1
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WIPO (PCT)
Prior art keywords
handle
core
fuel
boiling water
water reactor
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Application number
PCT/JP2017/025514
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French (fr)
Japanese (ja)
Inventor
清志 藤本
志郎 高橋
Original Assignee
日立Geニュークリア・エナジー株式会社
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Publication of WO2018021044A1 publication Critical patent/WO2018021044A1/en

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/33Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • the present invention relates to a core of a boiling water reactor, and in particular, a plurality of fuel assemblies are densely arranged in a triangular lattice arrangement, and a horizontal cross section is Y between three adjacent fuel assemblies.
  • the core of a boiling water reactor in which a control rod of a V shape is inserted.
  • Patent Document 1 A light water breeder reactor has been developed in which fuel assemblies are densely loaded in a triangular lattice arrangement in the core.
  • the lateral movement of the fuel assembly is prevented by a tab and a plate spring provided between the fuel assembly loaded in the light water breeder reactor and the core upper support plate, and An arrangement is described which ensures gap retention and control rod insertion.
  • Patent Document 1 discloses a configuration in which a hold down spring is provided between a fuel assembly and a core upper support plate to prevent floating of the fuel assembly.
  • it is a pressurized water reactor, in order to prevent floating of a fuel assembly, the structure which distribute
  • control rods and the place to insert control rods are different from those of boiling water reactors and the control rods are inserted into the center of the fuel assembly from the top, so it is unnecessary when inserting control rods The handle for moving the fuel assembly is removed.
  • the core upper support plate is installed at the core upper portion, and the core upper support plate and the fuel assembly having a horizontal cross section hexagonal shape are supported by the upper support mechanism (hold down spring).
  • the upper support mechanism hold down spring
  • the coolant flow path provided in the upper core support plate is smaller than the size of the fuel assembly having a horizontal cross section hexagonal shape. It is getting smaller.
  • the present invention provides a core of a boiling water reactor capable of improving work efficiency such as periodic inspection or refueling while preventing fuel floating during operation.
  • a boiling water atom in which fuel assemblies are densely arranged in a triangular lattice arrangement, and control rods with a horizontal cross section Y-shape are inserted at the center of three fuel assemblies.
  • the fuel assembly has a long side or a short side of an upper surface of a handle provided on three fuel assemblies surrounding the control rod having a horizontal cross-section Y-shape, the horizontal cross-section Y-shape
  • the fuel rod is provided with a fuel lift preventing member which is disposed to face the center of the control rod and is disposed above the upper surface of the handle to suppress the upward lift of the fuel assembly.
  • FIG. 3 is a partial plan view of the core showing the arrangement relationship between the fuel lifting prevention member and the fuel assembly of the first embodiment according to one embodiment of the present invention.
  • FIG. 2 is a partial plan view of the core with the fuel floating prevention member removed in FIG. 1; It is a longitudinal cross-sectional view of a boiling water reactor concerning one embodiment of the present invention. It is a longitudinal cross-sectional view of the fuel assembly with which the core of a boiling water reactor shown in FIG. 3 is loaded.
  • FIG. 5 is a partial plan view of the core showing the arrangement of the densely arranged fuel assemblies and control rods;
  • FIG. 3 is a sectional view taken along the line AA of FIG. 2 and is a partial side view of the upper part of the three fuel assemblies.
  • FIG. 1 It is a partial top view of the fuel floating prevention member shown in FIG. They are a partial plan view which shows the positional relationship of the grating
  • FIG. 1 It is a partial top view of the fuel floating prevention member of Example 2 which concerns on the other Example of this invention, and the DD cross section arrow line view.
  • FIG. 12 is a partial plan view showing a positional relationship between a grid member and a handle that constitute the fuel floating prevention member shown in FIG. 11 and a sectional view taken along the line E-E.
  • FIG. 12 is a partial plan view showing a positional relationship between a grid member and a handle constituting the fuel floating prevention member shown in FIG. 11 and a sectional view taken along the line F-F.
  • It is a fragmentary top view of a core showing arrangement relationship with a fuel floating prevention member and a fuel assembly of Example 3 concerning other examples of the present invention.
  • FIG. 15 is a sectional view taken along the line GG in FIG. 14 and showing the positional relationship between the fuel floating prevention member and the upper portion of the fuel assembly.
  • FIG. 18 is a partial plan view showing a positional relationship between a grid member and a handle constituting the fuel floating prevention member shown in FIG. 17 and a JJ sectional arrow view thereof.
  • FIG. 18 is a partial plan view showing a positional relationship between a grid member and a handle that constitute the fuel floating prevention member shown in FIG. 17 and a K-K cross sectional arrow view thereof. It is a fragmentary top view of a core showing arrangement relationship with a fuel floating prevention member and a fuel assembly of Example 6 concerning other examples of the present invention.
  • FIG. 3 shows a longitudinal sectional view of a boiling water reactor according to an embodiment of the present invention.
  • FIG. 3 shows a resource-renewable boiling water reactor (RBWR) as an example, it is not limited thereto.
  • RBWR resource-renewable boiling water reactor
  • ABWR Advanced Boiling Water Reactor
  • ABWR Advanced Boiling Water Reactor
  • ABWR Advanced Boiling Water Reactor
  • ABWR Advanced Boiling Water Reactor
  • ABWR Advanced Boiling Water Reactor
  • ABWR Advanced Boiling Water Reactor
  • a cylindrical core shroud 24 is provided in the reactor pressure vessel 20, and a plurality of fuel assemblies are provided in the core shroud 24.
  • the reactor core 21 loaded with is installed. Further, the axial upper end portion of the cylindrical core shroud 24 is covered with a shroud head 25 and disposed above the steam / water separator 27 and the steam / water separator 27 extending upward above the shroud head 25.
  • a steam dryer 28 is provided.
  • An annular downcomer 26 is formed between the reactor pressure vessel 20 and the core shroud 24.
  • An internal pump 14 is disposed in the downcomer 26.
  • Cooling water discharged from the internal pump 14 is supplied to the core 21 through the lower plenum 30.
  • the cooling water is heated as it passes through the core 21 to form a gas-liquid two-phase flow including water and steam.
  • the gas-water separator 27 separates the gas-liquid two-phase flow into steam and water.
  • the separated steam is further dehumidified by the steam dryer 28 and led to the main steam piping 29a.
  • the moisture-removed steam is directed to a steam turbine (not shown) to rotate the steam turbine.
  • a generator coupled to the steam turbine rotates to generate electrical power.
  • the steam discharged from the steam turbine is condensed into water by a condenser (not shown).
  • the condensed water is supplied as cooling water into the reactor pressure vessel 20 by the water supply pipe 29b.
  • the water separated by the steam separator 27 and the steam dryer 28 falls and reaches the downcomer 26 as cooling water.
  • a control rod capable of inserting control rods having a plurality of Y-shaped horizontal sections (cross sections) into the core 21
  • a control rod drive mechanism is provided in a control rod drive mechanism housing provided with a guide pipe and installed below the bottom of the reactor pressure vessel 20, and the control rod is connected to the control rod drive mechanism.
  • the control rod having a Y-shaped horizontal cross section (cross section) has three wings extending outward from the tie rod (or center post) located at the center, and each wing is a neutron absorbing material It has a plurality of neutron absorbing rods filled with B 4 C.
  • a control rod having a Y-shaped horizontal cross section (cross section) is formed between three fuel assemblies adjacent to each other. Is inserted.
  • the core 21 is supported by a core support plate 22, and a plurality of fuel assemblies, for example, about 700 fuel assemblies are loaded in the core 21. Further, as shown in FIG. 3, a fuel floating prevention member 31 is provided above the handle provided at the upper portion of the fuel assembly to suppress the floating of the fuel assembly to the upper side.
  • FIG. 4 is a longitudinal sectional view of a fuel assembly loaded in the core of the resource reuse type boiling water reactor (RBWR) shown in FIG.
  • the fuel assembly 1 includes a plurality of fuel rods 2, an upper tie plate 3, a lower tie plate 4, a plurality of fuel spacers 6, a channel box 5, and a handle 7.
  • the handle 7 is provided to be held by a crane or the like when loading the fuel assembly 1 into the core 21 or replacing the fuel assembly 1.
  • the fuel rod 2 is filled with a plurality of fuel pellets (not shown) in a sealed cladding tube (not shown).
  • the lower tie plate 4 supports the lower end of each fuel rod 2, and the upper tie plate 3 holds the upper end of each fuel rod 2.
  • the lower part of the lower tie plate 4 constituting the fuel assembly 1 is fitted in the three upper openings 9 provided in the fuel support fitting 8 arranged to penetrate the core support plate 22 in the lower part of the fuel assembly 1. Be supported.
  • a control rod moving opening 10 is provided at the center of the fuel support 8 so that the horizontal cross section (horizontal cross section) of the control rod can be moved up and down.
  • an elastic body 33 is disposed between the upper surface of the handle 7 provided on the top of the fuel assembly 1 and the grid member 32 disposed above the handle 7.
  • a part of the upper surface of the handle 7 is in contact with the lower surface of the grid member 32 via the elastic body 33.
  • the axial upper end surface of the elastic body 33 is fixed to the lower surface of the lattice member 32 to form a fuel floating prevention member 31.
  • the axial direction lower end surface (the surface on the opposite side of the lower surface of the grid member 32 of the elastic body 33) of the elastic body 33 constituting the fuel floating prevention member 31 is fixed to the handle 7 constituting the fuel assembly 1. Without contact. Note that, instead of this configuration, the axial direction lower end surface of the elastic body 33 may be fixed to a part of the upper surface of the handle 7 constituting the fuel assembly 1.
  • the elastic member 33 fixed to a part of the upper surface of the handle 7 cooperates with the lattice member 32 to constitute the fuel floating prevention member 31.
  • the upper grid plate and the upper portion disclosed in the above-mentioned Patent Document 1 by including the fuel floating preventing member 31. There is no need for the upper support mechanism for connecting the grid plate and the upper tie plate.
  • FIG. 5 is a partial plan view of the core 21 showing the arrangement of the densely arranged fuel assemblies 1 and the control rods 11.
  • each fuel assembly 1 is densely arranged by bundling a plurality of fuel rods in a triangular lattice in a channel box 5 having a horizontal cross section (cross section) having a hexagonal shape.
  • a control rod 11 having a Y-shaped horizontal cross section (cross section) is disposed between three fuel assemblies which are disposed adjacent to each other in the form of a triangular lattice.
  • a resource-recycling boiling water reactor is a boiling water reactor (BWR) in which the volume ratio of water to fuel is reduced by densely loading a plurality of fuel assemblies 1 into a core 21 as described above. ).
  • Resource recycling type boiling water reactor has a plutonium breeding ratio higher than that of conventional boiling water reactor (BWR), and the generation and consumption of fissile plutonium during reactor operation Can be approximately the same, and the growth ratio can be about 1.0.
  • the nuclear reactor is operated by nuclear fission of fuel in the fuel assembly 1, but the proportion of uranium-235 to undergo nuclear fission decreases with the passage of operation time, so the fuel is systematically replaced with new one
  • the fuel is systematically replaced with new one
  • a control rod 11 having a Y-shaped horizontal cross section (cross section) At the time of refueling, it is necessary to insert a control rod 11 having a Y-shaped horizontal cross section (cross section) to prevent reactor criticality, and at the time of refueling, a control rod 11 having a Y cross section (horizontal cross section)
  • the handle 7 is provided at the upper part of the fuel assembly 1 for moving the fuel assembly, so that refueling can be performed without changing the arrangement of the handle 7 at the time of reactor operation. Is desirable.
  • a conventional boiling water type atom in which a plurality of fuel rods are arranged in a square grid shape in a channel box having a rectangular horizontal cross section (cross section) and a plurality of fuel assemblies are loaded in a square grid shape in a core
  • the number of fuel rods per fuel assembly can be increased.
  • the weight per fuel rod is reduced, the weight of the entire fuel assembly is reduced as compared to a conventional boiling water reactor.
  • the pipe diameter of the cladding of the fuel rods densely arranged in the form of a triangular lattice in the fuel assembly 1 is reduced.
  • the installation distance in the axial direction of the fuel spacer 6 is narrowed compared to the case of the conventional boiling water reactor. Narrowing the installation interval of the fuel spacer 6 means that the number of the installed fuel spacers 6 increases, and the pressure loss to the cooling water flowing upward in the fuel assembly 1 increases, and the fuel assembly 1 At the same time, the fluid force acting to lift axially upward also increases.
  • the lower tie plate 4 may be disengaged from the insertion portion of the fuel support 8 and contact with other structures, possibly causing damage to the fuel assembly 1.
  • FIG. 3 and FIG. 4 providing the fuel floating prevention member 31 in the axial direction of the fuel assembly 1 has technical significance.
  • the fuel floating prevention member 31 is comprised with the lattice member 32 and the elastic body 33 is demonstrated as an example below, it is not restricted to this, The fuel floating prevention member 31 is comprised only with the lattice member 32, This fuel floating up Needless to say, the elastic body 33 may be disposed between the preventing member 31 and the upper surface of the handle 7 of the fuel assembly 1.
  • FIG. 1 is a partial plan view of a core showing an arrangement relationship between a fuel lifting prevention member 31 and a fuel assembly 1 according to a first embodiment of the present invention
  • FIG. 2 is a view showing the fuel lifting in FIG.
  • FIG. 7 is a partial plan view of the core with the prevention member 31 removed.
  • RBWR resource recycling type boiling water reactor
  • FIG. 1 and FIG. 2 ten fuel assemblies 1 out of a plurality of fuel assemblies 1 loaded in the core 21 and three fuel assemblies (for example, fuel assemblies) disposed apart from each other A control rod 11 (indicated by a dotted line in FIG.
  • each fuel assembly 1 a plurality of fuel rods are densely arranged in a triangular lattice by bundling a plurality of fuel rods in a channel box 5 having a hexagonal horizontal cross section (cross section).
  • a control rod 11 having a Y-shaped horizontal cross section (cross section) is disposed between three fuel assemblies which are disposed adjacent to each other in the form of a triangular lattice.
  • the control rod 11 having a Y-shaped horizontal cross section (cross section) includes three wings arranged at an interval of 120 degrees from one another.
  • a lattice member 32 constituting the fuel floating prevention member 31 disposed above the plurality of fuel assemblies 1 has a shape in which triangular lattices are two-dimensionally connected.
  • the grid member 32 constituting the fuel lift prevention member 31 has a repeated pattern of triangular grids.
  • the lattice member 32a intersects with the long side 71a of the upper surface of the handle 7a constituting the fuel assembly 1a
  • the lattice member 32b intersects the long side 71b of the upper surface of the handle 7b constituting the fuel assembly 1b.
  • a grid member 32 is disposed to intersect the long side 71c of the upper surface of the handle 7c constituting the fuel assembly 1c.
  • a horizontal cross section (cross section) is formed between the fuel assembly 1a, the fuel assembly 1b, and the fuel assembly 1c, which are three fuel assemblies arranged adjacent to each other in a triangular lattice.
  • a Y-shaped control rod 11 is disposed, and a connection portion between the grid member 32a, the grid member 32b, and the grid member 32c is a tie rod (or center) having a horizontal cross section (cross section) at the center of the control rod 11 It is located almost directly above the post) (not shown).
  • the grid member 32a intersects with the long side 71a of the upper surface of the handle 7a (a side defining both side surfaces along the longitudinal direction of the handle 7a) so that the intersecting position is the substantially central portion of the long side 71a. It is.
  • the grid member 32b intersects with the long side 71b of the upper surface of the handle 7b (side defining both side surfaces along the longitudinal direction of the handle 7b) so as to intersect substantially at the center of the long side 71b. It is a department.
  • the grid member 32c intersects with the long side 71c on the upper surface of the handle 7c (a side defining both side surfaces along the longitudinal direction of the handle 7c) so as to be substantially orthogonal to it. It is.
  • the above-mentioned relationship is similarly applied to the three fuel assemblies 1 adjacent to each other in the form of a triangular lattice and the lattice members 32 disposed above the three fuel assemblies 1. .
  • the grid members 32 constituting the fuel floating prevention member 31 so as to intersect the long side of the handle 7 constituting the fuel assembly 1, the cooling water above the respective fuel assemblies 1 (cooling It is possible to secure a flow path of cooling water (coolant) having a wide area without blocking the flow path of the material) by the grid member 32.
  • the long side 71a of the upper surface of the handle 7a constituting the fuel assembly 1a, the long side 71b of the upper surface of the handle 7b constituting the fuel assembly 1b, and the handle 7c constituting the fuel assembly 1c The three fuel assemblies 1a to 1c are arranged such that the long side 71c of the upper surface is directed to the tie rod (or center post) (not shown) which is the center of the Y-shaped control rod 11 in the horizontal cross section (horizontal cross section).
  • the core 21 is loaded.
  • Such an arrangement relationship is based on the fact that the horizontal cross section (cross section) between the three fuel assemblies and the three fuel assemblies 1 arranged in a triangular lattice adjacent to each other is Y-shaped.
  • the handles 7a to 7c of the three fuel assemblies 1a to 1c closely arranged in the form of a triangular lattice adjacent to each other so that the horizontal cross section (cross section) surrounds the Y-shaped control rod 11 Since all the long sides 71a to 71c on the top face are directed to the tie rod (or center post) which is the center of the Y-shaped control rod 11, the handle during reactor operation The periodic inspection or the fuel replacement can be performed without changing the arrangement of 7a to 7c, and the workability can be improved.
  • the short side 72a of the upper surface of the handle 7a constituting the fuel assembly 1a (the side defining both end portions in the longitudinal direction of the handle 7a) and the fuel assembly 1b
  • Short side 72b of the upper surface of the handle 7b (side defining both ends in the longitudinal direction of the handle 7b) and short side 71c of the upper surface of the handle 7c constituting the fuel assembly 1c (both ends of the handle 7c in the longitudinal direction Side
  • the horizontal cross section (cross section) is directed to a tie rod (or center post) (not shown) which is the center of the Y-shaped control rod 11. It is distributed without.
  • each fuel assembly 1a to 1c has a configuration in which a plurality of fuel rods are bundled in a triangular lattice and densely arranged in the channel box 5 having a horizontal cross section (cross section) in a hexagonal shape.
  • the channel box 5 has six side surfaces extending in the axial direction.
  • the horizontal cross section (cross section) is disposed at a distance of 120 from each other centering on a tie rod (or center post) (not shown) constituting the Y-shaped control rod 11.
  • the fuel assembly contact prevention pads 13 are provided near the upper end portions of the four side faces except the two side faces of the channel box 5 facing the two wings.
  • control rod contact prevention pads 12 are provided in the vicinity of the upper portions of the side surfaces of the two surfaces of the channel box 5 facing the two wings.
  • FIG. 6 a state in which one wing constituting the control rod 11 having a Y-shaped horizontal cross section (cross section) is disposed between the fuel assembly 1b and the fuel assembly 1c disposed adjacent to each other Is shown.
  • FIG. 6 shows a state in which the control rod 11 having a Y-shaped horizontal cross section (cross section) is inserted to the top.
  • the surfaces other than the side surfaces of the channel box 5 on the side where the control rod 11 with a Y-shaped horizontal cross section (cross section) is inserted are the channels of other adjacent fuel assemblies 1.
  • the fuel assembly 1b has a gap between the fuel assembly 1b and two adjacent fuel assemblies into which control rods 11 having a Y-shaped horizontal cross section (cross section) are inserted. It is clearly narrower than the gap between the side surface of the channel box 5 and the side surface of the channel box 5 of the fuel assembly 1c. Therefore, as shown in FIG.
  • the thickness of the control rod contact prevention pad 12 is larger than the thickness of the fuel assembly contact prevention pad 13, and the control rod contact prevention pad 12 and the fuel provided on these fuel assemblies 1b When the control rod contact prevention pads 12 provided on the assembly 1c abut on each other, the insertion path of the control rod 11 having a Y-shaped horizontal cross section (cross section) is secured.
  • FIG. 7 is a partial plan view of the fuel lift preventing member 31 shown in FIG. 1
  • FIG. 8 is a partial plan showing the positional relationship between the grid member 32 and the handle 7 constituting the fuel lift preventing member 31 shown in FIG.
  • FIG. 9 is a partial plan view showing the positional relationship between the handle member 7 and the grid member 32 constituting the fuel floating prevention member 31 shown in FIG. 1 and FIG. FIG.
  • the planar shape of the lattice member 32 constituting the fuel floating prevention member 31 is a combination of the lattice member 32a, the lattice member 32b and the lattice member 32c in a triangular lattice shape, and each lattice member
  • the grid members 32a, the grid members 32b, and the grid members 32c are disposed above the handles 7a, the handles 7b, and the handles 7c as described above.
  • the grid member 32a is on the long side 71a of the top surface of the handle 7a
  • the grid member 32b is on the long side 71b of the top surface of the handle 7b
  • the grid member 32c is on the long side 71c of the handle 7c.
  • the fuel lift-off preventing member 31 can be realized with a simple and simple structure by the grid member 32 having a repeated pattern of triangular grids.
  • the grid member 32, the control rod contact preventing pad 12, and the fuel assembly contact preventing pad 13 which constitute the fuel lift preventing member 31 are made of, for example, stainless steel.
  • FIG. 8 is a portion in a state of being rotated 90 degrees clockwise or counterclockwise in the arrangement relationship between the fuel assembly 1a shown in FIG. 1 and the grid member 32a constituting the fuel floating prevention member 31.
  • FIG. 8 is a plan view
  • the lower view of FIG. 8 is a sectional view taken along the line BB in the upper view.
  • the grid members 32a intersect so as to be substantially orthogonal to the long side of the top surface of the handle 7a.
  • FIG. 9 shows the arrangement relationship between the fuel assembly 1a shown in FIG. 1 and the lattice member 32a constituting the fuel floating prevention member 31, and the lower drawing of FIG. It is C section arrow line view.
  • the axial upper end surface of the elastic body 33 is fixed to the lower surface of the lattice member 32a, and the fuel floating prevention member 31 is configured.
  • the axial direction lower end surface (the surface on the opposite side of the lower surface of the grid member 32a of the elastic member 33) of the elastic body 33 constituting the fuel floating prevention member 31 is fixed to the handle 7a constituting the fuel assembly 1a. Without contact.
  • the case where a coil spring is used as the elastic body 33 is shown as an example. As shown in the lower part of FIG.
  • a part of the upper surface of the handle 7a constituting the fuel assembly 1a is biased by the coil spring as the elastic member 33 in contact with the fuel assembly 1a. It is pressed by a certain pressing force. Even if the fluid force acts to lift the fuel assembly 1a upward in the axial direction by pressure loss to the cooling water, the fuel lift preventing member 31 and / or Or, the fuel assembly 1a can be prevented from being damaged.
  • the elastic body 33 is not limited to a coil spring, and a leaf spring or a bamboo spring may be used. Moreover, although the case where one coiled spring is used as the elastic body 33 is shown as an example in FIG.8 and FIG.9, the number of objects of the coiled spring as the elastic body 33 to install is not restricted to this, Two or more The coil spring may be installed. Further, in the present embodiment, one end (the upper end portion in the axial direction) of the coil spring as the elastic body 33 is fixed to the lower surface of the grid member 32a, but the present invention is not limited thereto.
  • one end (axially lower end) of the coil spring as the elastic body 33 is fixed to the upper surface of the handle 7a constituting the fuel assembly 1a, and the other end of the coil spring is not fixed to the lower surface of the grid member 32a. , And may be in contact with each other.
  • the coil spring as the elastic body 33 is immersed in the cooling water (coolant) in the reactor pressure vessel 20 for a long time, one end of the coil spring as the elastic body 33 is on the upper surface of the handle 7a. It is desirable to fix and replace the coil assembly as the elastic member 33 together with the fuel assembly 1a at the time of refueling or the like.
  • FIG. 10 shows the vicinity of the shroud head 25 in which the fuel floating prevention member 31 shown in FIG. 1 is installed.
  • FIG. 10 is a side view of the upper portion of the core 21 in the reactor pressure vessel 20.
  • the core 21 has an annular (ring-like) core support frame 23 on the side of the outermost periphery of the fuel assembly 1 densely arranged in a triangular lattice, that is, the side of the outermost fuel assembly 1.
  • the inner side surface (inner peripheral surface) of the core support frame 23 is shaped to have unevenness so as to match the shape of the outermost fuel assembly 1 (the channel box 5 having a hexagonal cross section).
  • the outer surface (outer peripheral surface) of the core support frame 23 has substantially the same shape and size as the inner surface (inner peripheral surface) of the cylindrical core shroud 24.
  • the core support frame 23 is fixed to a support (not shown) provided on the inner surface (inner peripheral surface) of the core shroud 24.
  • the fuel floating prevention member 31 is disposed above the handle 7 constituting the fuel assembly 1 densely arranged in the form of a triangular lattice.
  • the outermost periphery of the fuel floating prevention member 31 is supported by the core support frame 23.
  • the fuel floating prevention member 31 is fixed in both the horizontal direction and the vertical direction (axial direction) in the core 21.
  • a configuration in which the fuel floating prevention member 31 is supported by the core support frame 23 is shown as an example, but the present invention is not limited to this configuration.
  • a support member may be provided on the inner side surface (inner peripheral surface) of the core shroud 24, and the outermost periphery of the fuel floating prevention member 31 may be fixed by the support member.
  • the present embodiment it is possible to provide a core of a boiling water reactor capable of improving the working efficiency of periodic inspection or refueling while preventing fuel floating during operation.
  • the long sides of the upper surfaces of the handles of the three fuel assemblies closely arranged in the form of a triangular lattice adjacent to each other so as to surround the Y-shaped control rods are Y-shaped. Since the control rod is disposed to be directed to the center of the control rod, periodic inspection or refueling can be performed without changing the arrangement of the handle at the time of reactor operation, and the workability can be improved.
  • the long sides of the upper surfaces of the handles of the three fuel assemblies closely arranged in the form of a triangular lattice adjacent to each other so as to surround the Y-shaped control rods are intersected.
  • the grid member having the repeated pattern shape of the triangular grid the fuel floating prevention member can be realized with a simple and simple structure.
  • an elastic member such as a spring on a grid member having a repeated pattern of triangular grids to constitute a fuel floating prevention member, it is preferable to lift the fuel assembly upward in the axial direction. It is possible to prevent
  • FIG. 11 is a partial plan view of a fuel lifting prevention member of a second embodiment according to another embodiment of the present invention, and a sectional view taken along the line DD of FIG.
  • the present embodiment is different from the first embodiment in that a groove or a recess which can be fitted to a handle constituting the fuel assembly is provided on the lower surface of the lattice member constituting the fuel lifting prevention member.
  • the other configuration is the same as that of the first embodiment.
  • the same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
  • the left view of FIG. 11 has the same plan configuration of the grid member 32 constituting the fuel lift prevention member 31 as the grid member 32a, the grid member 32b, and the grid member similar to the configuration shown in FIG. 7 in the first embodiment described above.
  • Each of the grid members 32a, 32b, and 32c, as described above, includes the handle 7a of the fuel assembly 1a and the handle 7b of the fuel assembly 1b, as described above. It is disposed above the handle 7c of the fuel assembly 1c. Also, as described in FIG.
  • the grid member 32a is on the long side 71a of the top surface of the handle 7a
  • the grid member 32b is on the long side 71b of the top surface of the handle 7b
  • the grid member 32c is on the long side 71c of the handle 7c.
  • a grid member 32 constituting the fuel lift prevention member 31 is disposed to intersect.
  • FIG. 11 is a sectional view taken along the line DD in the left view. As shown in the right figure, a groove 34 (or a recess) is provided on the lower surface of the lattice member 32a constituting the fuel lift prevention member 31 at a position intersecting the upper surface of the handle 7 of the fuel assembly 1.
  • 12 is a partial plan view showing the positional relationship between the grid member 32a and the handle 7a constituting the fuel floating prevention member 31 shown in FIG. 11, and its EE cross section arrow view, and FIG. They are a partial plan view which shows the positional relationship of the grid member 32a which comprises the fuel floating prevention member 31 shown to, and a handle, and the FF cross section arrow directional view.
  • FIG. 12 is a partial view of the fuel assembly 1a shown in FIG. 1 and the grid member 32a of the fuel lift preventing member 31 rotated 90 degrees clockwise or counterclockwise.
  • FIG. 12 is a plan view, and the lower part of FIG. 12 is a sectional view taken along the line E-E in the upper view.
  • the grid members 32a intersect so as to be substantially orthogonal to the long side of the upper surface of the handle 7a.
  • the grid member 32a has a groove 34 (or a recess) obtained by forming a substantially trapezoidal notch on the lower surface.
  • the groove 34 (or the recess) is continuous in the width direction (short side direction) of the grid member 32 a.
  • the grid member 32 a includes the groove 34 (or the recess) continuous in the width direction.
  • the bottom of the groove 34 (or the recess) that is, the portion closest to the top surface of the grid member 32a in the lower part of FIG. 12, is flattened and one end of a coil spring as an elastic body 33 is fixed.
  • the short side of the upper surface of the handle 7a is held so that the opening width of the groove 34 (or recess) gradually expands toward the handle 7a side from the bottom of the groove 34 (or recess) to which one end of the coil spring is fixed. It has slopes on both sides.
  • the lattice member 32a can be easily positioned with respect to the handle 7a constituting the fuel assembly 1a. More specifically, the grid member 32 constituting the fuel lifting prevention member 31 having a repeated grid pattern of triangular grid is disposed above the plurality of fuel assemblies 1 densely loaded in the core 21 in the form of triangular grid. As shown in FIG. 10 described above, when fixed to the core support frame 23, the groove 34 (or the recess) provided on the lower surface of the lattice member 32 has an inclined surface. The groove 34 (or the recess) can be fitted on the upper surface of the handle 7 in a self-aligned manner through the inclined surface with respect to 7, and positioning of the grid member 32 with respect to the handle 7 constituting the fuel assembly 1 Becomes easy.
  • the groove 34 (or the recess) provided on the lower surface of the lattice member 32a is engaged with the handle 7a constituting the fuel assembly 1a.
  • displacement in the A direction indicated by a white arrow in the upper drawing of FIG. 12 that is, vibration or external force along the long side direction (longitudinal direction) of the grid member 32a is applied to the fuel assembly 1a
  • one of the two side surfaces along the longitudinal direction of the handle 7a abuts on the inclined surface of the groove 34 (or the recess) provided on the lower surface of the grid member 32a.
  • the groove 34 (or the recess) provided on the lower surface of the grid member 32 a has a function as a displacement restricting portion that restricts the displacement of the fuel assembly 1.
  • the function as the displacement restricting portion is the displacement of the fuel assembly 1b and the fuel assembly 1c also in the displacement in the B direction and the C direction indicated by white arrows in the left view of FIG.
  • a groove 34 (or a recess) provided on the lower surface of the grid member 32 b and the grid member 32 c regulates the movement.
  • the groove 34 (or the recess) provided on the lower surface of the grid member 32 functions as a displacement restricting portion of the fuel assembly 1, whereby the control rod contact preventing pad 12 shown in FIG. Also, it is not necessary to provide the fuel assembly contact prevention pad 13 on the side surface of the channel box 5 constituting the fuel assembly 1.
  • the groove 34 (or the recess) provided on the lower surface of the grid member 32 functions as a displacement restricting portion of the fuel assembly 1 to make the gap between the fuel assemblies 1 disposed adjacent to each other It becomes possible to secure a gap as an insertion path of the control rod 11 of horizontal cross section (cross section) Y-shape.
  • the opening width of the groove 34 (or the recess) provided on the lower surface of the grid member 32 may be larger than the width (short side) of the upper surface of the handle 7 to be fitted, and the opening width may be set appropriately.
  • the positioning of the grid member constituting the fuel floating prevention member with respect to the handle constituting the fuel assembly is facilitated. Further, according to the present embodiment, since the lower surface of the grid member constituting the fuel lift prevention member has a groove (or a recess) which can be fitted to the handle constituting the fuel assembly, the fuel assembly can be displaced. It becomes possible to regulate.
  • FIG. 14 is a partial plan view of the core showing the arrangement relationship between the fuel lift prevention member and the fuel assembly of Example 3 according to another example of the present invention
  • FIG. 15 is a GG cross section of FIG. It is an arrow view, Comprising: It is a figure which shows the positional relationship of a fuel floating prevention member and the upper part of a fuel assembly.
  • the fuel assemblies are displaced toward the Y-shaped control rod side on the lower surface of the grid members arranged to intersect with the fuel assembly handle.
  • the second embodiment differs from the first embodiment in that a fuel assembly displacement restricting portion for restricting the pressure is provided.
  • the other configuration is the same as that of the first embodiment.
  • the same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
  • the lattice members 32 constituting the fuel lift-up preventing member 31 are arranged to intersect the long sides of the upper surface of the handle 7a constituting the fuel assembly 1a, and Are arranged to intersect with the long side of the upper surface of the handle 7b constituting the fuel assembly 1b.
  • the axial direction upper end surface of the coil spring as the elastic body 33 is fixed to the lower surface of the lattice member 32a, and the fuel floating prevention member 31 is configured.
  • the axial direction lower end surface (surface of the elastic member 33 opposite to the lower surface of the grid member 32a) of the coil spring as the elastic member 33 constituting the fuel floating prevention member 31 is a handle constituting the fuel assembly 1a.
  • the axial direction upper end surface of the coil spring as the elastic body 33 is fixed to the lower surface of the lattice member 32c, and the fuel floating prevention member 31 is configured.
  • the axial direction lower end surface of the coil spring as the elastic body 33 constituting the fuel floating prevention member 31 is a handle constituting the fuel assembly 1c. It is in contact without being fixed to 7ca.
  • the protrusion projecting toward the fuel assembly 1a In the lower surface of the grid member 32a, in the area from the vicinity of the position where the coil spring as the elastic body 33 is fixed to the Y-shaped control rod 11, there is provided a protrusion projecting toward the fuel assembly 1a.
  • the convex portion provided on the lower surface of the lattice member 32a and the convex portion provided on the lower surface of the lattice member 32c are continuous through the connection portion of the lattice member 32a and the lattice member 32c, and the fuel assembly displacement regulating portion 35 Configure
  • the connection between the grid members 32a and 32c is located directly above the tie rod (or center post) (not shown) which is the center of the Y-shaped control rod 11. Further, as shown in FIG.
  • the end surface on the lattice member 32a side is the fuel assembly 1a from the lower surface of the lattice member 32a. It has an inclined surface which is relatively steeply inclined toward the center of the Y-shaped control rod 11 as it goes to the side.
  • the end face on the grid member 32c side is relatively toward the center of the Y-shaped control rod 11 as it goes from the lower surface of the grid member 32c to the fuel assembly 1c side. It has a steeply inclined slope.
  • the side surface on the center side of the Y-shaped control rod 11 is the fuel assembly displacement restricting portion It abuts on the inclined surface which is one end face of 35, and the displacement of the fuel assembly 1a in the A direction is restricted. Further, of the two side surfaces along the longitudinal direction of the handle 7c constituting the fuel assembly 1c, the side surface on the center side of the Y-shaped control rod 11 is inclined at the other end surface of the fuel assembly displacement restricting portion 35. It abuts on the surface, and the displacement of the fuel assembly 1c in the C direction is restricted.
  • the fuel assembly displacement restricting portion is provided on the lower surface of the lattice member constituting the fuel lift preventing member, so that the Y-shaped control rod side of the fuel assembly It is possible to regulate the displacement of the
  • FIG. 16 is a partial plan view of a fuel floating prevention member according to a fourth embodiment of the present invention, and a sectional view taken along the line HH and a sectional view taken along the line I-I.
  • the shape of the lower surface of the lattice member in the area other than the area intersecting with the handle decreases in width toward the lower side (the fuel assembly side).
  • This embodiment differs from the first embodiment in that the vertical cross-sectional shape is configured to be thin.
  • the other configuration is the same as that of the first embodiment.
  • the same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
  • the lattice members 32 constituting the fuel lift prevention member 31 are arranged to intersect the long side of the upper surface of the handle 7a constituting the fuel assembly 1a,
  • the grid member 32b is disposed to intersect the long side of the top surface of the handle 7b constituting the fuel assembly 1b, and the grid member 32c is disposed to intersect the long side of the top surface of the handle 7c constituting the fuel assembly 1c.
  • the HH cross-sectional shape of the grid member 32a in the upper view forms a square shape.
  • the position of the HH cross section corresponds to a position intersecting the long side of the upper surface of the handle 7a constituting the fuel assembly 1a.
  • the I-I cross-sectional shape of the grid member 32a in the upper drawing has a smaller width as the shape on the lower side goes downward (the fuel assembly side), ie, vertical cross-sectional shape Has a narrowing shape.
  • the position of the I-I cross section corresponds to a position not intersecting the long side of the upper surface of the handle 7a constituting the fuel assembly 1a.
  • the lattice member 32 constituting the fuel lift-up preventing member 31 of the present embodiment has a rectangular shape in vertical cross section to provide elasticity not shown.
  • the end of the coil spring as the body 33 is shaped so as to be easily fixed, and the vertical cross-sectional shape in the area not intersecting with the handle 7 decreases in width toward the lower side (fuel assembly side) on the lower side, that is, vertical By making the cross-sectional shape thin, pressure loss to cooling water (coolant) flowing upward through the fuel assembly 1 is reduced.
  • the fluid flowing out from the upper outlet of the fuel assembly 1 (cooling water) in the region other than the region intersecting the handle 7 that constitutes the fuel assembly 1 among the grid members 32 that constitute the fuel floating prevention member 31 Can collide with the grid member 32, the fluid force received by the grid member 32 can be reduced. As a result, it is possible to improve the soundness of the fuel floating prevention member 31.
  • FIG. 17 is a partial plan view of the core showing the arrangement relationship between the fuel uplift preventing member and the fuel assembly of a fifth embodiment according to another embodiment of the present invention.
  • the present embodiment is different from the first embodiment in that each of the lattice members constituting the fuel floating prevention member has a lattice expanding member extending corresponding to the upper surface of the handle constituting each fuel assembly.
  • the other configuration is the same as that of the first embodiment.
  • the same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
  • the lattice members 32 constituting the fuel floating prevention member 31 are the upper surfaces of the handle 7a.
  • a lattice expanding member 36a is extended corresponding to the upper surface of the handle 7a.
  • the area of the plane of the lattice expanding member 36a is equal to or larger than the area of the upper surface of the handle 7a.
  • the grid member 32a and the grid expanding member 36a are orthogonal to each other.
  • a grid member 32b arranged to intersect the long side of the upper surface of the handle 7b constituting the fuel assembly 1b extends at a position intersecting the long side of the upper surface of the handle 7b in correspondence with the upper surface of the handle 7b. It has a lattice expanding member 36b.
  • the area of the plane of the lattice expanding member 36b is equal to or larger than the area of the upper surface of the handle 7b, and the lattice member 32b and the lattice expanding member 36b are orthogonal to each other.
  • a grid member 32c arranged to intersect the long side of the upper surface of the handle 7c constituting the fuel assembly 1c extends in a position corresponding to the upper surface of the handle 7c at a position intersecting the long side of the upper surface of the handle 7c.
  • Grating expanding member 36c The area of the plane of the lattice expanding member 36c is equal to or larger than the area of the upper surface of the handle 7c, and the lattice member 32c and the lattice expanding member 36c are orthogonal to each other.
  • FIG. 18 is a partial plan view showing the positional relationship between the lattice member 32a, the lattice expanding member 36a and the handle 7a constituting the fuel floating prevention member 31 shown in FIG. 17 and its JJ cross section arrow view; 17 is a partial plan view showing a positional relationship between a grid member 32a, a lattice expanding member 36a, and a handle 7a constituting the fuel floating prevention member 31 shown in FIG. 17, and its K-K cross section arrow view.
  • the upper view of FIG. 18 is a portion in a state of being rotated 90 degrees clockwise or counterclockwise in the arrangement relationship between the fuel assembly 1a shown in FIG. 17 and the lattice member 32a constituting the fuel floating prevention member 31.
  • FIG. 18 is a portion in a state of being rotated 90 degrees clockwise or counterclockwise in the arrangement relationship between the fuel assembly 1a shown in FIG. 17 and the lattice member 32a constituting the fuel floating prevention member 31.
  • FIG. 18 is a plan view, and the lower part of FIG. 18 is a sectional view taken along the line JJ in the upper view.
  • the lattice expanding member 36a has the same length and the same width as the upper surface of the handle 7a constituting the fuel assembly 1a.
  • One end of a coil spring as the elastic body 33 is fixed to the lower surface of the lattice expanding member 36a, and one end of the coil spring as the elastic body 33 is in contact with the handle 7a without being fixed.
  • FIG. 19 The upper view of FIG. 19 is the same as the arrangement relationship between the fuel assembly 1a shown in FIG. 17 and the lattice member 32a and the lattice expanding member 36a, and the lower view of FIG. .
  • coil springs as two elastic bodies 33 are provided on the lower surface of the lattice expanding member 36 a so as to be mutually separated along the longitudinal direction and to be fixed at one end.
  • the other ends of the coil springs as the two elastic bodies 33 are in contact with the upper surface of the handle 7a without being fixed.
  • floating of the fuel assembly 1a in the axial direction can be prevented by the lattice expanding member 36a on the entire top surface of the handle 7a.
  • by providing the lattice expanding member 36a it becomes possible to arrange a plurality of coil springs as the elastic body 33, and a load on the coil spring (elastic body 33) per one It is also possible to reduce the
  • the lattice expanding members to the respective lattice members constituting the fuel floating prevention member, floating of the fuel assembly can be more effectively prevented.
  • the load on the elastic body disposed to prevent damage to the fuel floating prevention member and / or the fuel assembly can be reduced, and the life of the elastic body can be prolonged. It becomes.
  • FIG. 20 is a partial plan view of the core showing the arrangement relationship between the fuel uplift preventing member and the fuel assembly of a sixth embodiment according to another embodiment of the present invention.
  • the short sides of the upper surface of the handle constituting the fuel assembly are directed to the tie rod (or center post) which is the center of the Y-shaped control rod.
  • the embodiment differs from the first embodiment in that the assembly is loaded in the core, and the grid members constituting the fuel floating prevention member are arranged such that the connection portions of the plurality of grid members intersect the long side of the upper surface of the handle.
  • the other configuration is the same as that of the first embodiment.
  • the same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
  • control of a Y-shaped horizontal cross section (cross section) between the fuel assembly 1a, the fuel assembly 1b, and the fuel assembly 1c closely arranged in the form of a triangular lattice adjacent to each other A bar 11 is arranged.
  • Short side 72a of the upper surface of the handle 7a constituting the fuel assembly 1a (side defining both side surfaces along the longitudinal direction of the handle 7a), short side 72b of the upper surface of the handle 7b constituting the fuel assembly 1b (long side of the handle 7b Y-shaped control is a side that defines both sides along the direction, and a short side 72c of the top surface of the handle 7c that constitutes the fuel assembly 1c (a side that defines the two sides along the longitudinal direction of the handle 7c) It is arranged to be directed to a tie rod (or center post) (not shown) which is the center of the rod 11.
  • Such an arrangement relationship is such that Y-shaped control rods 11 are disposed between the three other fuel assemblies disposed adjacent to each other in a triangular lattice and the three fuel assemblies 1.
  • the handles 7a to 7c of the three fuel assemblies 1a to 1c closely arranged in the form of a triangular lattice adjacent to each other so that the horizontal cross section (cross section) surrounds the Y-shaped control rod 11 Since all the short sides 72a to 72c of the top face are directed to the tie rod (or center post) which is the center of the Y-shaped control rod 11, the handle during reactor operation
  • the periodic inspection or the fuel replacement can be performed without changing the arrangement of 7a to 7c, and the workability can be improved.
  • the lattice member 32 which comprises the fuel floating prevention member 31 is provided with the repeating pattern shape of a triangular lattice.
  • the grid member 32 disposed above the handle 7a of the fuel assembly 1a has a long side so as to be substantially orthogonal to the long side 71a of the upper surface of the handle 7a (a side defining both side surfaces along the longitudinal direction of the handle 7a)
  • the grid member 32e intersects the side 71a at a predetermined inclination angle.
  • connection portion of the grid member 32a, the grid member 32d, and the grid member 32e is located above the substantially central portion of the long side 71a.
  • a coil spring (not shown) as an elastic body 33 having one end fixed to the lower surface of the connecting portion of the grid members 32a, 32d and 32e and the other end abutting without being fixed to the upper surface of the handle 7a Is provided.
  • each fuel assembly 1 is prevented from rising at the connection portion of the three lattice members, so that the soundness of the fuel floating prevention member 31 configured by the lattice members 32 is improved.
  • the shape of the lower surface of the connection portion of the three grid members may be the same as that of the first embodiment (FIGS. 8 and 9) or the second embodiment (FIGS. 12 and 13) described above.
  • the lattice expanding member (FIGS. 17 to 19) shown in the fifth embodiment may be provided.
  • the shape of the lower surface of the region other than the connection portion may be the shape shown in the above-described fourth embodiment (lower right view in FIG. 16).
  • the fuel floating prevention member since the fuel assembly is prevented from floating at the connection portion of the plurality of grid members constituting the fuel floating prevention member, the fuel floating prevention member It is possible to further improve the soundness.
  • RBWR resource recycling type boiling water reactor
  • the present invention is not limited to this, and the horizontal cross section is not limited to this. If it is a core structure in which fuel assemblies having hexagonal channel boxes are densely loaded adjacent to each other in a triangular lattice, for example, an improved boiling water reactor (ABWR), highly economical simplified boiling It is equally applicable to a water reactor (ESBWR) or a conventional boiling water reactor (BWR) having a recirculation pump.
  • ABWR improved boiling water reactor
  • ESBWR water reactor
  • BWR conventional boiling water reactor
  • the boiling water nuclear reactor may be configured by combining the configurations shown in the above-mentioned Example 2 to Example 5 in any combination.
  • the groove 34 (or the recess) and the fuel assembly displacement restricting portion 35 may be provided on the lower surface of the lattice member 32 by combining the second embodiment and the third embodiment.
  • the second embodiment and the fourth embodiment are combined, and a groove 34 (or a recess) is provided on the lower surface of the grid member 32 in the area intersecting the handle, and the lower surface of the grid member 32 in the area other than the area intersecting the handle.
  • the vertical cross-sectional shape may be configured to be thin.
  • all the configurations of the embodiment 2 to the embodiment 5 may be combined, that is, two or more embodiments of the embodiment 2 to the embodiment 5 may be arbitrarily combined.
  • the present invention is not limited to the embodiments described above, but includes various modifications.
  • the embodiments described above are described in detail in order to explain the present invention in an easy-to-understand manner, and are not necessarily limited to those having all the configurations described.
  • 1, 1a, 1b, 1c fuel assembly
  • 2 fuel rod 3
  • upper tie plate 4 lower tie plate 5
  • channel box 6 fuel spacer , 7, 7a, 7b, 7c ... handle
  • 8 fuel support bracket, 9 ... top opening, 10 ... opening for control rod movement, 11 ...
  • control rod 12 ⁇ ⁇ ⁇ Control rod contact preventing pad 13, fuel assembly contact preventing pad 14, internal pump 20, reactor pressure vessel 21, core 22, core support plate 23, ⁇ ⁇ ⁇ Core support frame, 24 ⁇ ⁇ ⁇ Core shroud, 25 ⁇ ⁇ ⁇ Shroud head, 26 ⁇ ⁇ ⁇ down link, 27 ⁇ ⁇ ⁇ Air-water separator, 28 ⁇ ⁇ ⁇ Steam dryer, 29a ⁇ ⁇ ⁇ Main steam Piping, 29b ⁇ Water supply piping, 30 ⁇ ⁇ ⁇ Lower plenum, 31 ⁇ ⁇ ⁇ Fuel lifting preventing members 32, 32a, 32b, 32c, 32d, 32e: lattice members, 33: elastic bodies, 34: grooves, 35: fuel assembly displacement regulating portion, 36a, 36b, 36c, 36d, 36e ... lattice expanding members, 71a, 71b, 71c ... long sides, 72a, 72b, 72c ... short sides

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Abstract

Provided is a boiling-water reactor reactor-core capable of improving the work efficiency of periodic inspection, fuel replacement and so on while preventing fuel from floating up during the operation. In a boiling-water reactor reactor-core 21, fuel assemblies 1 are closely arranged in a triangular lattice arrangement, and a control rod 11, which has a Y-shaped horizontal cross section, is interposed at the center point among three fuel assemblies (1a-1c). The fuel assemblies 1 are disposed such that long sides (71a-71c) of the upper surfaces of handles (7a-7c) provided to the three fuel assemblies (1a-1c) that surround the control rod 11 having the Y-shaped horizontal cross section face the center of the control rod 11 having the Y-shaped horizontal cross section. The fuel assemblies 1 are provided with a fuel floating preventing member 31 that is disposed above the upper surfaces of the handles and helps prevent the fuel assemblies from floating upward.

Description

沸騰水型原子炉の炉心Boiling water reactor core
 本発明は、沸騰水型原子炉の炉心に係り、特に、複数体の燃料集合体が三角格子状配列にて稠密に配され、相互に隣接する3体の燃料集合体間に水平断面がY字型の制御棒が挿入される沸騰水型原子炉の炉心に関する。 The present invention relates to a core of a boiling water reactor, and in particular, a plurality of fuel assemblies are densely arranged in a triangular lattice arrangement, and a horizontal cross section is Y between three adjacent fuel assemblies. The core of a boiling water reactor in which a control rod of a V shape is inserted.
 炉心に燃料集合体が三角格子状配列にて稠密に装荷される軽水増殖炉が開発されている。例えば、特許文献1には、軽水増殖炉に装荷される燃料集合体と炉心上部支持板との間に設けたタブと板ばねにより燃料集合体の横への移動を防止し、燃料集合体のギャップ保持と制御棒の挿入性を確保する構成が記載されている。また、特許文献1には、燃料集合体と炉心上部支持板との間にホールドダウンスプリングを設け、燃料集合体の浮き上がりを防止する構成が開示されている。 
 また、加圧水型原子炉であるものの、特許文献2には、燃料集合体の浮き上がりを防止するために、燃料集合体上部ノズルの上面四辺に板ばねを配する構成が記載されている。
また、加圧水型原子炉では制御棒を挿入する方式及び制御棒を挿入する場所が、沸騰水型原子炉とは異なり、制御棒を燃料集合体中央に上部より挿入するため、制御棒挿入時に不要な燃料集合体移動用のハンドルは取り外される。
A light water breeder reactor has been developed in which fuel assemblies are densely loaded in a triangular lattice arrangement in the core. For example, according to Patent Document 1, the lateral movement of the fuel assembly is prevented by a tab and a plate spring provided between the fuel assembly loaded in the light water breeder reactor and the core upper support plate, and An arrangement is described which ensures gap retention and control rod insertion. Further, Patent Document 1 discloses a configuration in which a hold down spring is provided between a fuel assembly and a core upper support plate to prevent floating of the fuel assembly.
Moreover, although it is a pressurized water reactor, in order to prevent floating of a fuel assembly, the structure which distribute | arranges a leaf spring to the upper surface four sides of a fuel assembly upper nozzle is described in patent document 2. FIG.
Also, in a pressurized water reactor, the method of inserting control rods and the place to insert control rods are different from those of boiling water reactors and the control rods are inserted into the center of the fuel assembly from the top, so it is unnecessary when inserting control rods The handle for moving the fuel assembly is removed.
特開平8-220276号公報JP-A-8-220276 特開平8-36078号公報JP-A-8-36078
 しかしながら、特許文献1に記載される構成では、炉心上部に炉心上部支持板を設置し、炉心上部支持板と水平断面六角形状の燃料集合体を上部支持機構(ホールドダウンスプリング)で支持することで、燃料浮き上がりを防止している。炉心上部支持板には、各燃料集合体に対して上部支持機構を設置するスペースが必要となるため、炉心上部支持板に設ける冷却材流路は、水平断面六角形状の燃料集合体の大きさより小さくなっている。原子炉の冷却材循環ポンプ等への機器の負担を軽減するために、炉心上部支持板での圧損を低減する必要があり、そのためには広い冷却材流路を確保する必要が有る。また、上部支持機構としてホールドダウンスプリングを用いて燃料浮き上がりを防止しているが、複数の燃料集合体に対してホールドダウンスプリングを設置する必要があり、取り付けが困難となる。 
 また、特許文献2に記載される構成では、原子炉運転中、燃料集合体の中央に上方から制御棒を挿入する方式であるがゆえ、燃料集合体を移動するためのハンドルは取り外されている。従って、燃料交換時において、ハンドルを取り付ける作業が必要となり、燃料交換作業の効率化を図ることはできない。 
 そこで、本発明は、運転時における燃料浮き上がりを防止しつつ、定期検査或は燃料交換等の作業効率を向上し得る沸騰水型原子炉の炉心を提供する。
However, in the configuration described in Patent Document 1, the core upper support plate is installed at the core upper portion, and the core upper support plate and the fuel assembly having a horizontal cross section hexagonal shape are supported by the upper support mechanism (hold down spring). , To prevent fuel lift. Since the upper core support plate requires a space for installing the upper support mechanism with respect to each fuel assembly, the coolant flow path provided in the upper core support plate is smaller than the size of the fuel assembly having a horizontal cross section hexagonal shape. It is getting smaller. In order to reduce the burden of equipment on the coolant circulation pump of the reactor, it is necessary to reduce the pressure loss in the core upper support plate, and for that purpose, it is necessary to secure a wide coolant flow path. Although the fuel is prevented from floating by using the hold down spring as the upper support mechanism, it is necessary to install the hold down spring for a plurality of fuel assemblies, which makes installation difficult.
Further, in the configuration described in Patent Document 2, since the control rod is inserted from above into the center of the fuel assembly during reactor operation, the handle for moving the fuel assembly is removed. . Therefore, at the time of refueling, it is necessary to attach the handle, and it is not possible to improve the efficiency of the refueling operation.
Therefore, the present invention provides a core of a boiling water reactor capable of improving work efficiency such as periodic inspection or refueling while preventing fuel floating during operation.
 上記課題を解決するため、本発明は、燃料集合体が三角格子状配列で稠密に配置され、3体の燃料集合体の中心に水平断面Y字型の制御棒が挿入される沸騰水型原子炉の炉心であって、前記燃料集合体は、前記水平断面Y字型の制御棒を囲む3体の燃料集合体に設けられるハンドルの上面の長辺又は短辺が、前記水平断面Y字型の制御棒の中心に向くように配され、前記ハンドルの上面の上方に配され、前記燃料集合体の上方への浮き上がりを抑制する燃料浮き上がり防止部材を備えることを特徴とする。 In order to solve the above problems, according to the present invention, a boiling water atom in which fuel assemblies are densely arranged in a triangular lattice arrangement, and control rods with a horizontal cross section Y-shape are inserted at the center of three fuel assemblies. In the core of a furnace, the fuel assembly has a long side or a short side of an upper surface of a handle provided on three fuel assemblies surrounding the control rod having a horizontal cross-section Y-shape, the horizontal cross-section Y-shape The fuel rod is provided with a fuel lift preventing member which is disposed to face the center of the control rod and is disposed above the upper surface of the handle to suppress the upward lift of the fuel assembly.
 本発明によれば、運転時における燃料浮き上がりを防止しつつ、定期検査或は燃料交換等の作業効率を向上し得る沸騰水型原子炉の炉心を提供することが可能となる。 
 上記した以外の課題、構成及び効果は、以下の実施形態の説明により明らかにされる。
ADVANTAGE OF THE INVENTION According to this invention, it becomes possible to provide the core of the boiling water reactor which can improve operation | work efficiency, such as a regular test | inspection or refueling, preventing the floating of the fuel at the time of operation | use.
Problems, configurations, and effects other than those described above will be apparent from the description of the embodiments below.
本発明の一実施例に係る実施例1の燃料浮き上がり防止部材及び燃料集合体との配置関係を示す炉心の部分平面図である。FIG. 3 is a partial plan view of the core showing the arrangement relationship between the fuel lifting prevention member and the fuel assembly of the first embodiment according to one embodiment of the present invention. 図1において、燃料浮き上がり防止部材を取り外した状態における炉心の部分平面図である。FIG. 2 is a partial plan view of the core with the fuel floating prevention member removed in FIG. 1; 本発明の一実施形態に係る沸騰水型原子炉の縦断面図である。It is a longitudinal cross-sectional view of a boiling water reactor concerning one embodiment of the present invention. 図3に示す沸騰水型原子炉の炉心に装荷される燃料集合体の縦断面図である。It is a longitudinal cross-sectional view of the fuel assembly with which the core of a boiling water reactor shown in FIG. 3 is loaded. 稠密に配された燃料集合体と制御棒との配置関係を示す炉心の部分平面図である。FIG. 5 is a partial plan view of the core showing the arrangement of the densely arranged fuel assemblies and control rods; 図2のA-A断面矢視図であって、3体の燃料集合体の上部の部分側面図である。FIG. 3 is a sectional view taken along the line AA of FIG. 2 and is a partial side view of the upper part of the three fuel assemblies. 図1に示す燃料浮き上がり防止部材の部分平面図である。It is a partial top view of the fuel floating prevention member shown in FIG. 図1に示す燃料浮き上がり防止部材を構成する格子部材とハンドルとの位置関係を示す部分平面図と、そのB―B断面矢視図である。They are a partial plan view which shows the positional relationship of the grating | lattice member and handle which comprise the fuel floating prevention member shown in FIG. 1, and the BB cross section arrow line view. 図1に示す燃料浮き上がり防止部材を構成する格子部材とハンドルとの位置関係を示す部分平面図と、そのC―C断面矢視図である。They are a partial plan view which shows the positional relationship of the grating | lattice member and handle which comprise the fuel floating prevention member shown in FIG. 1, and its CC cross-section arrow line view. シュラウドヘッドの近傍であって、図1に示す燃料浮き上がり防止部材を設置した状態を示す図である。It is a figure which is the vicinity of a shroud head, and shows the state which installed the fuel floating prevention member shown in FIG. 本発明の他の実施例に係る実施例2の燃料浮き上がり防止部材の部分平面図と、そのD-D断面矢視図である。It is the partial top view of the fuel floating prevention member of Example 2 which concerns on the other Example of this invention, and the DD cross section arrow line view. 図11に示す燃料浮き上がり防止部材を構成する格子部材とハンドルとの位置関係を示す部分平面図と、そのE―E断面矢視図である。FIG. 12 is a partial plan view showing a positional relationship between a grid member and a handle that constitute the fuel floating prevention member shown in FIG. 11 and a sectional view taken along the line E-E. 図11に示す燃料浮き上がり防止部材を構成する格子部材とハンドルとの位置関係を示す部分平面図と、そのF―F断面矢視図である。FIG. 12 is a partial plan view showing a positional relationship between a grid member and a handle constituting the fuel floating prevention member shown in FIG. 11 and a sectional view taken along the line F-F. 本発明の他の実施例に係る実施例3の燃料浮き上がり防止部材及び燃料集合体との配置関係を示す炉心の部分平面図である。It is a fragmentary top view of a core showing arrangement relationship with a fuel floating prevention member and a fuel assembly of Example 3 concerning other examples of the present invention. 図14のG-G断面矢視図であって、燃料浮き上がり防止部材と燃料集合体の上部との位置関係を示す図である。FIG. 15 is a sectional view taken along the line GG in FIG. 14 and showing the positional relationship between the fuel floating prevention member and the upper portion of the fuel assembly. 本発明の他の実施例に係る実施例4の燃料浮き上がり防止部材の部分平面図と、そのH―H断面矢視図及びI―I断面矢視図である。They are a partial plan view of the fuel floating prevention member of Example 4 which concerns on the other Example of this invention, the HH cross section arrow line view, and an II cross section arrow line view. 本発明の他の実施例に係る実施例5の燃料浮き上がり防止部材及び燃料集合体との配置関係を示す炉心の部分平面図である。It is a fragmentary top view of a core showing arrangement relation with a fuel floating prevention member and a fuel assembly of Example 5 concerning other examples of the present invention. 図17に示す燃料浮き上がり防止部材を構成する格子部材とハンドルとの位置関係を示す部分平面図と、そのJ―J断面矢視図である。FIG. 18 is a partial plan view showing a positional relationship between a grid member and a handle constituting the fuel floating prevention member shown in FIG. 17 and a JJ sectional arrow view thereof. 図17に示す燃料浮き上がり防止部材を構成する格子部材とハンドルとの位置関係を示す部分平面図と、そのK―K断面矢視図である。FIG. 18 is a partial plan view showing a positional relationship between a grid member and a handle that constitute the fuel floating prevention member shown in FIG. 17 and a K-K cross sectional arrow view thereof. 本発明の他の実施例に係る実施例6の燃料浮き上がり防止部材及び燃料集合体との配置関係を示す炉心の部分平面図である。It is a fragmentary top view of a core showing arrangement relationship with a fuel floating prevention member and a fuel assembly of Example 6 concerning other examples of the present invention.
 先ず、図3に本発明の一実施形態に係る沸騰水型原子炉の縦断面図を示す。図3では、資源再利用型沸騰水型原子炉(Resource-Renewable Boiling Water Reactor:RBWR)を一例として示すが、これに限られるものでは無い。例えば、改良型沸騰水型原子炉(Advanced Boiling Water Reactor:ABWR)、再循環ポンプを備え減速材としての冷却水を原子炉圧力容器外へ通流し再び原子炉圧力容器内のダウンカマへ流入させることで冷却水を循環させる通常の沸騰水型原子炉(BWR)、或は、チムニによる冷却水の自然循環方式を用いることで、BWRにおける再循環ポンプ、ABWRにおけるインターナルポンプを不要とする高経済性単純化沸騰水型原子炉(Economic Simplified Boiling Water Reactor:ESBWR)等、その他の原子炉へも同様に適用可能である。すなわち、沸騰水型原子炉であれば、いずれの構成においても以下に説明する本発明の構成を適用可能である。 First, FIG. 3 shows a longitudinal sectional view of a boiling water reactor according to an embodiment of the present invention. Although FIG. 3 shows a resource-renewable boiling water reactor (RBWR) as an example, it is not limited thereto. For example, an advanced boiling water reactor (Advanced Boiling Water Reactor: ABWR), a recirculation pump, and cooling water as a moderator through the reactor pressure vessel and flowing it back to the downcomer in the reactor pressure vessel. High economy that eliminates the need for the recirculation pump in BWR and the internal pump in ABWR by using the normal boiling water reactor (BWR) that circulates the cooling water in the tank or the natural circulation system of the cooling water by chimney The present invention is similarly applicable to other reactors such as the Economic Simplified Boiling Water Reactor (ESBWR). That is, as long as it is a boiling water reactor, the configuration of the present invention described below can be applied to any configuration.
 図3に示すように、資源再利用型沸騰水型原子炉(RBWR)は、原子炉圧力容器20内に円筒状の炉心シュラウド24が設けられ、炉心シュラウド24内に、複数体の燃料集合体が装荷された炉心21が配設されている。また、円筒状の炉心シュラウド24の軸方向上端部はシュラウドヘッド25で覆われており、このシュラウドヘッド25上部に上方へと延伸する気水分離器27及び、気水分離器27の上方に配される蒸気乾燥器28が設けられている。原子炉圧力容器20と炉心シュラウド24の間には円環状のダウンカマ26が形成されている。ダウンカマ26内には、インターナルポンプ14が配設されている。 As shown in FIG. 3, in the resource recycling type boiling water reactor (RBWR), a cylindrical core shroud 24 is provided in the reactor pressure vessel 20, and a plurality of fuel assemblies are provided in the core shroud 24. The reactor core 21 loaded with is installed. Further, the axial upper end portion of the cylindrical core shroud 24 is covered with a shroud head 25 and disposed above the steam / water separator 27 and the steam / water separator 27 extending upward above the shroud head 25. A steam dryer 28 is provided. An annular downcomer 26 is formed between the reactor pressure vessel 20 and the core shroud 24. An internal pump 14 is disposed in the downcomer 26.
 インターナルポンプ14から吐出された冷却水は、下部プレナム30を経て炉心21に供給される。冷却水は、炉心21を通過する際に加熱されて水及び蒸気を含む気液二相流となる。気水分離器27は気液二相流を蒸気と水に分離する。分離された蒸気は、更に蒸気乾燥器28で湿分が除去されて主蒸気配管29aに導かれる。この湿分が除去された蒸気は、蒸気タービン(図示せず)に導かれ、蒸気タービンを回転させる。蒸気タービンに連結された発電機が回転し、電力を発生する。蒸気タービンから排出された蒸気は、復水器(図示せず)で凝縮されて水となる。この凝縮水は、冷却水として給水配管29bにより原子炉圧力容器20内に供給される。気水分離器27及び蒸気乾燥器28で分離された水は、落下して冷却水としてダウンカマ26内に達する。 Cooling water discharged from the internal pump 14 is supplied to the core 21 through the lower plenum 30. The cooling water is heated as it passes through the core 21 to form a gas-liquid two-phase flow including water and steam. The gas-water separator 27 separates the gas-liquid two-phase flow into steam and water. The separated steam is further dehumidified by the steam dryer 28 and led to the main steam piping 29a. The moisture-removed steam is directed to a steam turbine (not shown) to rotate the steam turbine. A generator coupled to the steam turbine rotates to generate electrical power. The steam discharged from the steam turbine is condensed into water by a condenser (not shown). The condensed water is supplied as cooling water into the reactor pressure vessel 20 by the water supply pipe 29b. The water separated by the steam separator 27 and the steam dryer 28 falls and reaches the downcomer 26 as cooling water.
 なお、原子炉圧力容器20の下部プレナム30には、燃料集合体の核反応を制御するため、炉心21へ複数の水平断面(横断面)がY字型の制御棒を挿入可能とする制御棒案内管が設けられ、原子炉圧力容器20の底部よりも下方に設置された制御棒駆動機構ハウジング内に制御棒駆動機構を備え、制御棒は制御棒駆動機構に連結されている。ここで、水平断面(横断面)がY字型の制御棒は、中心に位置するタイロッド(またはセンタポスト)から外側に向かって延伸する3枚の翼を備え、各翼は中性子吸収材であるBCが充填された複数の中性子吸収棒を有する。これら3枚の翼は、タイロッド(またはセンタポスト)の周囲に相互に120度の間隔にて配されている。そして、炉心21に三角格子状に稠密に装荷される複数体の燃料集合体のうち、相互に隣接する3体の燃料集合体の間に、水平断面(横断面)がY字型の制御棒が1本挿入される。 In addition, in order to control the nuclear reaction of the fuel assembly in the lower plenum 30 of the reactor pressure vessel 20, a control rod capable of inserting control rods having a plurality of Y-shaped horizontal sections (cross sections) into the core 21 A control rod drive mechanism is provided in a control rod drive mechanism housing provided with a guide pipe and installed below the bottom of the reactor pressure vessel 20, and the control rod is connected to the control rod drive mechanism. Here, the control rod having a Y-shaped horizontal cross section (cross section) has three wings extending outward from the tie rod (or center post) located at the center, and each wing is a neutron absorbing material It has a plurality of neutron absorbing rods filled with B 4 C. These three wings are arranged at intervals of 120 degrees around the tie rods (or center posts). Then, among a plurality of fuel assemblies densely loaded in the core 21 in the form of a triangular lattice, a control rod having a Y-shaped horizontal cross section (cross section) is formed between three fuel assemblies adjacent to each other. Is inserted.
 炉心21は、炉心支持板22に支持され、炉心21内には複数体の燃料集合体、例えば、約700体の燃料集合体が装荷されている。また、図3に示すように燃料集合体の上部に設けられるハンドルの上方に、燃料集合体の上方への浮き上がりを抑制するための燃料浮き上がり防止部材31が設けられている。 The core 21 is supported by a core support plate 22, and a plurality of fuel assemblies, for example, about 700 fuel assemblies are loaded in the core 21. Further, as shown in FIG. 3, a fuel floating prevention member 31 is provided above the handle provided at the upper portion of the fuel assembly to suppress the floating of the fuel assembly to the upper side.
 図4は、図3に示す資源再利用型沸騰水型原子炉(RBWR)の炉心に装荷される燃料集合体の縦断面図である。図4に示すように、燃料集合体1は、複数の燃料棒2、上部タイプレート3、下部タイプレート4、複数の燃料スペーサ6、チャンネルボックス5、及びハンドル7を備えている。ハンドル7は、燃料集合体1の炉心21への装荷又は燃料集合体1の交換時にクレーン等により把持するために設けられている。また、燃料棒2は、複数の燃料ペレット(図示せず)を、密封された被覆管(図示せず)内に充填している。
下部タイプレート4は各燃料棒2の下端部を支持し、上部タイプレート3は各燃料棒2の上端部を保持する。燃料集合体1の下部は、炉心支持板22を貫通するよう配される燃料支持金具8に設けられた3つの上部開口部9に、燃料集合体1を構成する下部タイプレート4の下部が嵌合し支持される。燃料支持金具8の中央には、水平断面(横断面)がY字型の制御棒を上下に移動できるように制御棒移動用開口部10が設けられている。
FIG. 4 is a longitudinal sectional view of a fuel assembly loaded in the core of the resource reuse type boiling water reactor (RBWR) shown in FIG. As shown in FIG. 4, the fuel assembly 1 includes a plurality of fuel rods 2, an upper tie plate 3, a lower tie plate 4, a plurality of fuel spacers 6, a channel box 5, and a handle 7. The handle 7 is provided to be held by a crane or the like when loading the fuel assembly 1 into the core 21 or replacing the fuel assembly 1. Further, the fuel rod 2 is filled with a plurality of fuel pellets (not shown) in a sealed cladding tube (not shown).
The lower tie plate 4 supports the lower end of each fuel rod 2, and the upper tie plate 3 holds the upper end of each fuel rod 2. The lower part of the lower tie plate 4 constituting the fuel assembly 1 is fitted in the three upper openings 9 provided in the fuel support fitting 8 arranged to penetrate the core support plate 22 in the lower part of the fuel assembly 1. Be supported. A control rod moving opening 10 is provided at the center of the fuel support 8 so that the horizontal cross section (horizontal cross section) of the control rod can be moved up and down.
 図4に示すように、燃料集合体1の上部に設けられるハンドル7の上面と、ハンドル7の上方に配される格子部材32との間に弾性体33が配されている。換言すれば、ハンドル7の上面の一部は、弾性体33を介して格子部材32の下面に接している。これにより、仮に、燃料集合体1が軸方向上方へと浮き上がるよう変位した場合であっても、弾性体33及び格子部材32により、上記浮き上がりの変位は抑制される。すなわち、燃料集合体1の浮き上がりが防止される。なお、弾性体33が燃料集合体1の上部に設けられるハンドル7の上面と格子部材32の下面との間に介在することで、格子部材32及び/又はハンドル7を有する燃料集合体1の損傷を回避でき、良好に燃料集合体1の浮き上がりを防止することができる。 
 弾性体33の軸方向上端面が、格子部材32の下面に固定され燃料浮き上がり防止部材31が構成される。この場合、燃料浮き上がり防止部材31を構成する弾性体33の軸方向下端面(弾性体33の格子部材32の下面とは反対側の面)は、燃料集合体1を構成するハンドル7に固定されることなく、当接している。なお、この構成に代えて、弾性体33の軸方向下端面を、燃料集合体1を構成するハンドル7の上面の一部に固定する構成としても良い。この場合、ハンドル7の上面の一部に固定された弾性体33と、格子部材32とが協働することで燃料浮き上がり防止部材31を構成することになる。このように、本実施形態の資源再利用型沸騰水型原子炉(RBWR)の炉心では、燃料浮き上がり防止部材31を備えることにより、上記特許文献1に開示される、上部格子板、及び、上部格子板と上部タイプレートを接続するための上部支持機構が不要となる。
As shown in FIG. 4, an elastic body 33 is disposed between the upper surface of the handle 7 provided on the top of the fuel assembly 1 and the grid member 32 disposed above the handle 7. In other words, a part of the upper surface of the handle 7 is in contact with the lower surface of the grid member 32 via the elastic body 33. Thus, even if the fuel assembly 1 is displaced so as to float upward in the axial direction, the above-described displacement of the floating is suppressed by the elastic body 33 and the lattice member 32. That is, the floating of the fuel assembly 1 is prevented. The elastic body 33 intervenes between the upper surface of the handle 7 provided on the upper portion of the fuel assembly 1 and the lower surface of the grid member 32 to damage the fuel assembly 1 having the grid member 32 and / or the handle 7. As a result, the floating of the fuel assembly 1 can be well prevented.
The axial upper end surface of the elastic body 33 is fixed to the lower surface of the lattice member 32 to form a fuel floating prevention member 31. In this case, the axial direction lower end surface (the surface on the opposite side of the lower surface of the grid member 32 of the elastic body 33) of the elastic body 33 constituting the fuel floating prevention member 31 is fixed to the handle 7 constituting the fuel assembly 1. Without contact. Note that, instead of this configuration, the axial direction lower end surface of the elastic body 33 may be fixed to a part of the upper surface of the handle 7 constituting the fuel assembly 1. In this case, the elastic member 33 fixed to a part of the upper surface of the handle 7 cooperates with the lattice member 32 to constitute the fuel floating prevention member 31. As described above, in the core of the resource reuse type boiling water reactor (RBWR) according to the present embodiment, the upper grid plate and the upper portion disclosed in the above-mentioned Patent Document 1 by including the fuel floating preventing member 31. There is no need for the upper support mechanism for connecting the grid plate and the upper tie plate.
 図5は、稠密に配された燃料集合体1と制御棒11との配置関係を示す炉心21の部分平面図である。図5に示すように、各燃料集合体1は、水平断面(横断面)が六角形状のチャンネルボックス5内に複数本の燃料棒を三角格子状に束ねて稠密に配している。また、相互に隣接して三角格子状に配される3体の燃料集合体の間に、水平断面(横断面)がY字型の制御棒11が配されている。資源再利用型沸騰水型原子炉(RBWR)は、このように複数体の燃料集合体1を炉心21に稠密に装荷することで、水対燃料体積比を低減した沸騰水型原子炉(BWR)である。資源再利用型沸騰水型原子炉(RBWR)は、従来の沸騰水型原子炉(BWR)と比較してプルトニウム増殖比を高めており、原子炉運転時における核分裂性プルトニウムの発生量と消費量をほぼ同一にでき、増殖比を約1.0とすることが可能である。 FIG. 5 is a partial plan view of the core 21 showing the arrangement of the densely arranged fuel assemblies 1 and the control rods 11. As shown in FIG. 5, each fuel assembly 1 is densely arranged by bundling a plurality of fuel rods in a triangular lattice in a channel box 5 having a horizontal cross section (cross section) having a hexagonal shape. Further, a control rod 11 having a Y-shaped horizontal cross section (cross section) is disposed between three fuel assemblies which are disposed adjacent to each other in the form of a triangular lattice. A resource-recycling boiling water reactor (RBWR) is a boiling water reactor (BWR) in which the volume ratio of water to fuel is reduced by densely loading a plurality of fuel assemblies 1 into a core 21 as described above. ). Resource recycling type boiling water reactor (RBWR) has a plutonium breeding ratio higher than that of conventional boiling water reactor (BWR), and the generation and consumption of fissile plutonium during reactor operation Can be approximately the same, and the growth ratio can be about 1.0.
 ここで、原子炉は、燃料集合体1内の燃料の核分裂により運転されているが、運転時間の経過と共に核分裂を行うウラン-235の割合が少なくなるため、計画的に燃料を新しいものに交換する必要がある。燃料交換時には原子炉臨界防止のため、水平断面(横断面)がY字型の制御棒11を挿入する必要があり、燃料交換時には、水平断面(横断面)がY字型の制御棒11、及び水平断面(横断面)がY字型の制御棒と隣接する3体の燃料集合体1の組み合わせで燃料交換することが合理的である。上述のように燃料集合体1の上部には、燃料集合体移動用にハンドル7が設けられており、原子炉運転時におけるハンドル7の配置を変更することなく、燃料交換を実施できるようにすることが望ましい。 Here, the nuclear reactor is operated by nuclear fission of fuel in the fuel assembly 1, but the proportion of uranium-235 to undergo nuclear fission decreases with the passage of operation time, so the fuel is systematically replaced with new one There is a need to. At the time of refueling, it is necessary to insert a control rod 11 having a Y-shaped horizontal cross section (cross section) to prevent reactor criticality, and at the time of refueling, a control rod 11 having a Y cross section (horizontal cross section) And it is rational to refuel in the combination of three fuel assemblies 1 in which the horizontal cross section (cross section) of the Y-shaped control rod and the adjacent fuel assembly 1 are adjacent. As described above, the handle 7 is provided at the upper part of the fuel assembly 1 for moving the fuel assembly, so that refueling can be performed without changing the arrangement of the handle 7 at the time of reactor operation. Is desirable.
 また、水平断面(横断面)が四角形状のチャンネルボックス内に複数の燃料棒を正方格子状に配すると共に、複数体の燃料集合体を炉心に正方格子状に装荷する従来の沸騰水型原子炉に対して、資源再利用型沸騰水型原子炉(RBWR)では、燃料集合体一体当たりの燃料棒の本数を増大できる。しかしながら、燃料棒一本当たりの重量が軽くなるため、燃料集合体全体では、従来の沸騰水型原子炉と比較して重量は軽くなる。また、資源再利用型沸騰水型原子炉(RBWR)では、燃料集合体1内に三角格子状に稠密に配される燃料棒の被覆管の管径が小さくなる。そのため、仮に、従来の沸騰水型原子炉と同様の間隔にて軸方向に離間し燃料スペーサ6を配し、燃料棒を支持する構成とした場合、燃料スペーサ6による支持部間の中央の燃料棒2の水平方向の変位量が大きくなり、他の燃料棒2と接触する事態が生じることが予想される。そこで、上述の図4に示したように、従来の沸騰水型原子炉の場合と比較して、燃料スペーサ6の軸方向の設置間隔を狭くしている。
燃料スペーサ6の設置間隔を狭くすることは、燃料スペーサ6の設置個数が増えることを意味し、燃料集合体1内を上方へと通流する冷却水に対する圧損が増大し、燃料集合体1を軸方向上方へと浮き上がらせるよう作用する流体力も同時に増大する。仮に、燃料集合体1が軸方向上方へと浮き上がると、燃料支持金具8の挿し込み部から下部タイプレート4が離脱し、他の構造物に接触し、燃料集合体1の損傷に至る可能性が懸念される。そのため、図3及び図4に示したように、燃料集合体1の軸方向上方に燃料浮き上がり防止部材31を備えることに技術的意義を有するのである。以下では、格子部材32及び弾性体33にて燃料浮き上がり防止部材31を構成する場合を一例として説明するが、これに限られず、燃料浮き上がり防止部材31を格子部材32のみで構成し、この燃料浮き上がり防止部材31と燃料集合体1のハンドル7の上面との間に、弾性体33を配する構成としても良いことは言うまでもない。 
 以下、図面を用いて本発明の実施例について、燃料浮き上がり防止部材31を中心に詳細説明する。
In addition, a conventional boiling water type atom in which a plurality of fuel rods are arranged in a square grid shape in a channel box having a rectangular horizontal cross section (cross section) and a plurality of fuel assemblies are loaded in a square grid shape in a core With respect to the reactor, in the resource recycling type boiling water reactor (RBWR), the number of fuel rods per fuel assembly can be increased. However, because the weight per fuel rod is reduced, the weight of the entire fuel assembly is reduced as compared to a conventional boiling water reactor. Further, in the resource reuse type boiling water reactor (RBWR), the pipe diameter of the cladding of the fuel rods densely arranged in the form of a triangular lattice in the fuel assembly 1 is reduced. Therefore, assuming that the fuel spacer 6 is axially separated at a distance similar to that of the conventional boiling water reactor and the fuel rods are supported, the central fuel between the support portions of the fuel spacers 6 is used. It is expected that the amount of horizontal displacement of the rod 2 will be large and contact with other fuel rods 2 will occur. Therefore, as shown in FIG. 4 described above, the installation distance in the axial direction of the fuel spacer 6 is narrowed compared to the case of the conventional boiling water reactor.
Narrowing the installation interval of the fuel spacer 6 means that the number of the installed fuel spacers 6 increases, and the pressure loss to the cooling water flowing upward in the fuel assembly 1 increases, and the fuel assembly 1 At the same time, the fluid force acting to lift axially upward also increases. If the fuel assembly 1 floats upward in the axial direction, the lower tie plate 4 may be disengaged from the insertion portion of the fuel support 8 and contact with other structures, possibly causing damage to the fuel assembly 1. Are concerned. Therefore, as shown in FIG. 3 and FIG. 4, providing the fuel floating prevention member 31 in the axial direction of the fuel assembly 1 has technical significance. Although the case where the fuel floating prevention member 31 is comprised with the lattice member 32 and the elastic body 33 is demonstrated as an example below, it is not restricted to this, The fuel floating prevention member 31 is comprised only with the lattice member 32, This fuel floating up Needless to say, the elastic body 33 may be disposed between the preventing member 31 and the upper surface of the handle 7 of the fuel assembly 1.
Hereinafter, an embodiment of the present invention will be described in detail focusing on the fuel floating prevention member 31 with reference to the drawings.
 図1は、本発明の一実施例に係る実施例1の燃料浮き上がり防止部材31及び燃料集合体1との配置関係を示す炉心の部分平面図であり、図2は、図1において、燃料浮き上がり防止部材31を取り外した状態における炉心の部分平面図である。上述したように、資源再利用型沸騰水型原子炉(RBWR)では、炉心21(図3)に、例えば、約700体の燃料集合体1が装荷さている。図1及び図2では、炉心21に装荷される複数体の燃料集合体1のうち10体の燃料集合体1と、相互に離接して配される3体の燃料集合体(例えば、燃料集合体1a~1c)の間に配置される水平断面(横断面)がY字型の制御棒11(図1では点線で示す)を一例として示す。図5に示したように、各燃料集合体1は、水平断面(横断面)が六角形状のチャンネルボックス5内に複数本の燃料棒を三角格子状に束ねて稠密に配している。また、相互に隣接して三角格子状に配される3体の燃料集合体の間に、水平断面(横断面)がY字型の制御棒11が配されている。水平断面(横断面)がY字型の制御棒11は、相互に120度の間隔にて配される3枚の翼を備える。 FIG. 1 is a partial plan view of a core showing an arrangement relationship between a fuel lifting prevention member 31 and a fuel assembly 1 according to a first embodiment of the present invention, and FIG. 2 is a view showing the fuel lifting in FIG. FIG. 7 is a partial plan view of the core with the prevention member 31 removed. As described above, in the resource recycling type boiling water reactor (RBWR), for example, about 700 fuel assemblies 1 are loaded in the core 21 (FIG. 3). In FIG. 1 and FIG. 2, ten fuel assemblies 1 out of a plurality of fuel assemblies 1 loaded in the core 21 and three fuel assemblies (for example, fuel assemblies) disposed apart from each other A control rod 11 (indicated by a dotted line in FIG. 1) having a Y-shaped horizontal section (cross section) disposed between the bodies 1a to 1c) is shown as an example. As shown in FIG. 5, in each fuel assembly 1, a plurality of fuel rods are densely arranged in a triangular lattice by bundling a plurality of fuel rods in a channel box 5 having a hexagonal horizontal cross section (cross section). Further, a control rod 11 having a Y-shaped horizontal cross section (cross section) is disposed between three fuel assemblies which are disposed adjacent to each other in the form of a triangular lattice. The control rod 11 having a Y-shaped horizontal cross section (cross section) includes three wings arranged at an interval of 120 degrees from one another.
 図1に示すように、複数体の燃料集合体1の上方に配される燃料浮き上がり防止部材31を構成する格子部材32は、三角格子が二次元的に連なる形状を有する。換言すれば、燃料浮き上がり防止部材31を構成する格子部材32は、三角格子の繰り返しパターン形状を備える。例えば、格子部材32aは、燃料集合体1aを構成するハンドル7a上面の長辺71aと交差し、格子部材32bは、燃料集合体1bを構成するハンドル7b上面の長辺71bと交差し、格子部材32cは、燃料集合体1cを構成するハンドル7c上面の長辺71cと交差するよう、格子部材32が配されている。これら、相互に隣接して三角格子状に配される3体の燃料集合体である、燃料集合体1a、燃料集合体1b、及び燃料集合体1cの間には、水平断面(横断面)がY字型の制御棒11が配され、格子部材32a、格子部材32b、及び格子部材32cの接続部は、水平断面(横断面)がY字型の制御棒11の中心であるタイロッド(またはセンタポスト)(図示せず)のほぼ直上に位置している。また、格子部材32aはハンドル7a上面の長辺71a(ハンドル7aの長手方向に沿った両側面を画定する辺)と略直交するよう交差し、その交差する位置は、長辺71aの略中央部である。同様に、格子部材32bはハンドル7b上面の長辺71b(ハンドル7bの長手方向に沿った両側面を画定する辺)と略直交するよう交差し、その交差する位置は、長辺71bの略中央部である。また、格子部材32cはハンドル7c上面の長辺71c(ハンドル7cの長手方向に沿った両側面を画定する辺)と略直交するよう交差し、その交差する位置は、長辺71cの略中央部である。 As shown in FIG. 1, a lattice member 32 constituting the fuel floating prevention member 31 disposed above the plurality of fuel assemblies 1 has a shape in which triangular lattices are two-dimensionally connected. In other words, the grid member 32 constituting the fuel lift prevention member 31 has a repeated pattern of triangular grids. For example, the lattice member 32a intersects with the long side 71a of the upper surface of the handle 7a constituting the fuel assembly 1a, and the lattice member 32b intersects the long side 71b of the upper surface of the handle 7b constituting the fuel assembly 1b. A grid member 32 is disposed to intersect the long side 71c of the upper surface of the handle 7c constituting the fuel assembly 1c. A horizontal cross section (cross section) is formed between the fuel assembly 1a, the fuel assembly 1b, and the fuel assembly 1c, which are three fuel assemblies arranged adjacent to each other in a triangular lattice. A Y-shaped control rod 11 is disposed, and a connection portion between the grid member 32a, the grid member 32b, and the grid member 32c is a tie rod (or center) having a horizontal cross section (cross section) at the center of the control rod 11 It is located almost directly above the post) (not shown). The grid member 32a intersects with the long side 71a of the upper surface of the handle 7a (a side defining both side surfaces along the longitudinal direction of the handle 7a) so that the intersecting position is the substantially central portion of the long side 71a. It is. Similarly, the grid member 32b intersects with the long side 71b of the upper surface of the handle 7b (side defining both side surfaces along the longitudinal direction of the handle 7b) so as to intersect substantially at the center of the long side 71b. It is a department. The grid member 32c intersects with the long side 71c on the upper surface of the handle 7c (a side defining both side surfaces along the longitudinal direction of the handle 7c) so as to be substantially orthogonal to it. It is.
 上述の関係は、他の相互に隣接して三角格子状に配される3体の燃料集合体1と、これら3体の燃料集合体1の上方に配される格子部材32についても同様である。このように、燃料浮き上がり防止部材31を構成する格子部材32を、燃料集合体1を構成するハンドル7の長辺と交差するよう配することで、各燃料集合体1の上方の冷却水(冷却材)の流路を格子部材32により大きく塞ぐことなく、広い面積の冷却水(冷却材)の流路を確保することが可能となる。また、燃料集合体1内を上方へと通流する冷却水に対する圧損の増加を抑制することも可能となる。 The above-mentioned relationship is similarly applied to the three fuel assemblies 1 adjacent to each other in the form of a triangular lattice and the lattice members 32 disposed above the three fuel assemblies 1. . As described above, by arranging the grid members 32 constituting the fuel floating prevention member 31 so as to intersect the long side of the handle 7 constituting the fuel assembly 1, the cooling water above the respective fuel assemblies 1 (cooling It is possible to secure a flow path of cooling water (coolant) having a wide area without blocking the flow path of the material) by the grid member 32. In addition, it is also possible to suppress an increase in pressure loss for the cooling water flowing upward through the fuel assembly 1.
 また、図2に示すように、燃料集合体1aを構成するハンドル7a上面の長辺71a、燃料集合体1bを構成するハンドル7b上面の長辺71b、及び、燃料集合体1cを構成するハンドル7c上面の長辺71cは、水平断面(横断面)がY字型の制御棒11の中心であるタイロッド(またはセンタポスト)(図示せず)に向かうよう、3体の燃料集合体1a~1cが炉心21に装荷されている。このような配置関係は、相互に隣接して三角格子状に配される他の3体の燃料集合体と、これら3体の燃料集合体1間に水平断面(横断面)がY字型の制御棒11が配される場合においても同様である。このように、水平断面(横断面)がY字型の制御棒11を囲むよう、相互に隣接して三角格子状に稠密に配される3体の燃料集合体1a~1cのハンドル7a~7c上面の長辺71a~71cの全てが、水平断面(横断面)がY字型の制御棒11の中心であるタイロッド(またはセンタポスト)に向くよう配されることから、原子炉運転時におけるハンドル7a~7cの配置を変更することなく、定期検査或いは燃料交換等を実施でき、作業性を向上することが可能となる。 Further, as shown in FIG. 2, the long side 71a of the upper surface of the handle 7a constituting the fuel assembly 1a, the long side 71b of the upper surface of the handle 7b constituting the fuel assembly 1b, and the handle 7c constituting the fuel assembly 1c The three fuel assemblies 1a to 1c are arranged such that the long side 71c of the upper surface is directed to the tie rod (or center post) (not shown) which is the center of the Y-shaped control rod 11 in the horizontal cross section (horizontal cross section). The core 21 is loaded. Such an arrangement relationship is based on the fact that the horizontal cross section (cross section) between the three fuel assemblies and the three fuel assemblies 1 arranged in a triangular lattice adjacent to each other is Y-shaped. The same applies to the case where the control rod 11 is disposed. Thus, the handles 7a to 7c of the three fuel assemblies 1a to 1c closely arranged in the form of a triangular lattice adjacent to each other so that the horizontal cross section (cross section) surrounds the Y-shaped control rod 11 Since all the long sides 71a to 71c on the top face are directed to the tie rod (or center post) which is the center of the Y-shaped control rod 11, the handle during reactor operation The periodic inspection or the fuel replacement can be performed without changing the arrangement of 7a to 7c, and the workability can be improved.
 これに対し、図1及び図2に示されるように、燃料集合体1aを構成するハンドル7a上面の短辺72a(ハンドル7aの長手方向の両端部を画定する辺)、燃料集合体1bを構成するハンドル7b上面の短辺72b(ハンドル7bの長手方向の両端部を画定する辺)、及び、燃料集合体1cを構成するハンドル7c上面の短辺71c(ハンドル7cの長手方向の両端部を画定する辺)は、いずれの格子部材32と交差することなく、また、水平断面(横断面)がY字型の制御棒11の中心であるタイロッド(またはセンタポスト)(図示せず)に向かうことなく配される。これは、他の燃料集合体1を構成するハンドル7においても同様である。 On the other hand, as shown in FIGS. 1 and 2, the short side 72a of the upper surface of the handle 7a constituting the fuel assembly 1a (the side defining both end portions in the longitudinal direction of the handle 7a) and the fuel assembly 1b Short side 72b of the upper surface of the handle 7b (side defining both ends in the longitudinal direction of the handle 7b) and short side 71c of the upper surface of the handle 7c constituting the fuel assembly 1c (both ends of the handle 7c in the longitudinal direction Side does not intersect with any grid member 32, and the horizontal cross section (cross section) is directed to a tie rod (or center post) (not shown) which is the center of the Y-shaped control rod 11. It is distributed without. The same applies to the handles 7 constituting the other fuel assemblies 1.
 図6は、図2のA-A断面矢視図であって、3体の燃料集合体1a~1cの上部の部分側面図である。図6に示すように、3体の燃料集合体1a~1cの上部には、燃料集合体をクレーンで吊って移動可能とするハンドル7a、7b、7cがそれぞれ設けられている。また、各燃料集合体1a~1cは、上述のとおり水平断面(横断面)が六角形状のチャンネルボックス5内に複数本の燃料棒を三角格子状に束ねて稠密に配する構成であることから、チャンネルボックス5は、軸方向に延伸する6面の側面を有する。これら、6面の側面のうち、水平断面(横断面)がY字型の制御棒11を構成するタイロッド(またはセンタポスト)(図示せず)を中心とし相互に120の間隔にて配される3枚の翼のうち、2枚の翼と対向するチャンネルボックス5の2面の側面を除く、4面の側面の上端部付近には、それぞれ、燃料集合体接触防止パッド13が設けられている。一方、上記2枚の翼と対向するチャンネルボックス5の2面の側面の上部付近には、それぞれ、制御棒接触防止パッド12が設けられている。図6では、隣接して配される燃料集合体1bと燃料集合体1cとの間に、水平断面(横断面)がY字型の制御棒11を構成する1枚の翼が配さている状態を示している。 6 is a sectional view taken along the line AA in FIG. 2 and is a partial side view of the upper part of the three fuel assemblies 1a to 1c. As shown in FIG. 6, handles 7a, 7b, and 7c are provided above the three fuel assemblies 1a to 1c to allow the fuel assemblies to be suspended by a crane for movement. Further, as described above, each fuel assembly 1a to 1c has a configuration in which a plurality of fuel rods are bundled in a triangular lattice and densely arranged in the channel box 5 having a horizontal cross section (cross section) in a hexagonal shape. The channel box 5 has six side surfaces extending in the axial direction. Among the six side surfaces, the horizontal cross section (cross section) is disposed at a distance of 120 from each other centering on a tie rod (or center post) (not shown) constituting the Y-shaped control rod 11. Among the three wings, the fuel assembly contact prevention pads 13 are provided near the upper end portions of the four side faces except the two side faces of the channel box 5 facing the two wings. . On the other hand, control rod contact prevention pads 12 are provided in the vicinity of the upper portions of the side surfaces of the two surfaces of the channel box 5 facing the two wings. In FIG. 6, a state in which one wing constituting the control rod 11 having a Y-shaped horizontal cross section (cross section) is disposed between the fuel assembly 1b and the fuel assembly 1c disposed adjacent to each other Is shown.
 図6では、水平断面(横断面)がY字型の制御棒11が最上部まで挿入された状態を示している。また、図2に示したように、水平断面(横断面)がY字型の制御棒11が挿入される側のチャンネルボックス5の側面以外の面は、隣接する他の燃料集合体1のチャンネルボックス5の側面との間に間隙を有するが、この間隙は、水平断面(横断面)がY字型の制御棒11が挿入される隣接する2つの燃料集合体である、燃料集合体1bのチャンネルボックス5の側面と、燃料集合体1cのチャンネルボックス5の側面との間隙よりも明らかに狭い。従って、図6に示すように、制御棒接触防止パッド12の厚さは、燃料集合体接触防止パッド13の厚さよりも大きく、これら燃料集合体1bに設けられた制御棒接触防止パッド12と燃料集合体1cに設けられた制御棒接触防止パッド12とが当接することにより、水平断面(横断面)がY字型の制御棒11の挿入路が確保される。 FIG. 6 shows a state in which the control rod 11 having a Y-shaped horizontal cross section (cross section) is inserted to the top. Further, as shown in FIG. 2, the surfaces other than the side surfaces of the channel box 5 on the side where the control rod 11 with a Y-shaped horizontal cross section (cross section) is inserted are the channels of other adjacent fuel assemblies 1. The fuel assembly 1b has a gap between the fuel assembly 1b and two adjacent fuel assemblies into which control rods 11 having a Y-shaped horizontal cross section (cross section) are inserted. It is clearly narrower than the gap between the side surface of the channel box 5 and the side surface of the channel box 5 of the fuel assembly 1c. Therefore, as shown in FIG. 6, the thickness of the control rod contact prevention pad 12 is larger than the thickness of the fuel assembly contact prevention pad 13, and the control rod contact prevention pad 12 and the fuel provided on these fuel assemblies 1b When the control rod contact prevention pads 12 provided on the assembly 1c abut on each other, the insertion path of the control rod 11 having a Y-shaped horizontal cross section (cross section) is secured.
 図7は、図1に示す燃料浮き上がり防止部材31の部分平面図であり、図8は、図1に示す燃料浮き上がり防止部材31を構成する格子部材32とハンドル7との位置関係を示す部分平面図と、そのB―B断面矢視図、図9は、図1に示す燃料浮き上がり防止部材31を構成する格子部材32とハンドル7との位置関係を示す部分平面図と、そのC―C断面矢視図である。 FIG. 7 is a partial plan view of the fuel lift preventing member 31 shown in FIG. 1, and FIG. 8 is a partial plan showing the positional relationship between the grid member 32 and the handle 7 constituting the fuel lift preventing member 31 shown in FIG. FIG. 9 is a partial plan view showing the positional relationship between the handle member 7 and the grid member 32 constituting the fuel floating prevention member 31 shown in FIG. 1 and FIG. FIG.
 図7に示すように、燃料浮き上がり防止部材31を構成する格子部材32の平面形状は、格子部材32a、格子部材32b、及び格子部材32cを三角格子状に組み合わせたものであり、それぞれの格子部材32a、格子部材32b、及び格子部材32cは、上述したように各ハンドル7a、ハンドル7b、及びハンドル7cの上方に配される。また、図1にて説明したように、格子部材32aをハンドル7a上面の長辺71aに、格子部材32bをハンドル7b上面の長辺71bに、また、格子部材32cをハンドル7cの長辺71cに交差するよう、燃料浮き上がり防止部材31を構成する格子部材32を配することで、三角格子の繰り返しパターン形状を備える格子部材32にて、容易且つ単純な構造にて燃料浮き上がり防止部材31を実現できる。 
 なお、燃料浮き上がり防止部材31を構成する格子部材32、制御棒接触防止パッド12、及び燃料集合体接触防止パッド13は、例えば、ステンレス鋼製である。
As shown in FIG. 7, the planar shape of the lattice member 32 constituting the fuel floating prevention member 31 is a combination of the lattice member 32a, the lattice member 32b and the lattice member 32c in a triangular lattice shape, and each lattice member The grid members 32a, the grid members 32b, and the grid members 32c are disposed above the handles 7a, the handles 7b, and the handles 7c as described above. Also, as described in FIG. 1, the grid member 32a is on the long side 71a of the top surface of the handle 7a, the grid member 32b is on the long side 71b of the top surface of the handle 7b, and the grid member 32c is on the long side 71c of the handle 7c. By arranging the grid members 32 constituting the fuel lift-up preventing member 31 to intersect with each other, the fuel lift-off preventing member 31 can be realized with a simple and simple structure by the grid member 32 having a repeated pattern of triangular grids. .
The grid member 32, the control rod contact preventing pad 12, and the fuel assembly contact preventing pad 13 which constitute the fuel lift preventing member 31 are made of, for example, stainless steel.
 図8の上図は、図1に示した燃料集合体1aと燃料浮き上がり防止部材31を構成する格子部材32aとの配置関係において、時計回り又は反時計回りに90度回転させた状態での部分平面図であり、図8の下図は、上図のB-B断面矢視図である。図8の上図に示すように、格子部材32aは、ハンドル7a上面の長辺と略直交するよう交差している。
 また、図9の上図は、図1に示した燃料集合体1aと燃料浮き上がり防止部材31を構成する格子部材32aとの配置関係を示しており、図9の下図は、上図のC-C断面矢視図である。図8の下図及び図9の下図に示すように、弾性体33の軸方向上端面が、格子部材32aの下面に固定され燃料浮き上がり防止部材31が構成される。この場合、燃料浮き上がり防止部材31を構成する弾性体33の軸方向下端面(弾性体33の格子部材32aの下面とは反対側の面)は、燃料集合体1aを構成するハンドル7aに固定されることなく、当接している。本実施例では、弾性体33として、コイルばねを用いる場合を一例として示している。図9の下図に示すように、燃料集合体1aを構成するハンドル7aの上面の一部は、当接する弾性体33としてのコイルばねにより付勢され、燃料集合体1aは軸方向下方へと適度な押圧力により押圧されている。仮に、冷却水に対する圧損により燃料集合体1aを軸方向上方へと浮き上がらせるよう流体力が作用した場合であっても、弾性体33としてのコイルばねのばね力により、燃料浮き上がり防止部材31及び/又は燃料集合体1aが損傷することを防止できる。
The upper view of FIG. 8 is a portion in a state of being rotated 90 degrees clockwise or counterclockwise in the arrangement relationship between the fuel assembly 1a shown in FIG. 1 and the grid member 32a constituting the fuel floating prevention member 31. FIG. 8 is a plan view, and the lower view of FIG. 8 is a sectional view taken along the line BB in the upper view. As shown in the upper drawing of FIG. 8, the grid members 32a intersect so as to be substantially orthogonal to the long side of the top surface of the handle 7a.
Further, the upper drawing of FIG. 9 shows the arrangement relationship between the fuel assembly 1a shown in FIG. 1 and the lattice member 32a constituting the fuel floating prevention member 31, and the lower drawing of FIG. It is C section arrow line view. As shown in the lower side of FIG. 8 and the lower side of FIG. 9, the axial upper end surface of the elastic body 33 is fixed to the lower surface of the lattice member 32a, and the fuel floating prevention member 31 is configured. In this case, the axial direction lower end surface (the surface on the opposite side of the lower surface of the grid member 32a of the elastic member 33) of the elastic body 33 constituting the fuel floating prevention member 31 is fixed to the handle 7a constituting the fuel assembly 1a. Without contact. In the present embodiment, the case where a coil spring is used as the elastic body 33 is shown as an example. As shown in the lower part of FIG. 9, a part of the upper surface of the handle 7a constituting the fuel assembly 1a is biased by the coil spring as the elastic member 33 in contact with the fuel assembly 1a. It is pressed by a certain pressing force. Even if the fluid force acts to lift the fuel assembly 1a upward in the axial direction by pressure loss to the cooling water, the fuel lift preventing member 31 and / or Or, the fuel assembly 1a can be prevented from being damaged.
 なお、弾性体33として、コイルばねに限らず、板ばね或いは竹の子ばね等を用いても良い。また、図8及び図9では、弾性体33として1つのコイルばねを用いる場合を一例として示しているが、設置する弾性体33としてのコイルばねの個数はこれに限られるものではなく、複数個のコイルばねを設置する構成としてもよい。また、本実施例では、弾性体33としてのコイルばねの一端(軸方向上端部)を格子部材32aの下面に固定する構成としたがこれに限られるものではない。例えば、弾性体33としてのコイルばねの一端(軸方向下方端)を、燃料集合体1aを構成するハンドル7aの上面に固定し、コイルばねの他端を格子部材32aの下面に固定することなく、当接させる構成としても良い。
但し、長期に渡り原子炉圧力容器20内の冷却水(冷却材)に、弾性体33としてのコイルばねが浸漬することを考慮すると、弾性体33としてのコイルばねの一端をハンドル7aの上面に固定し、燃料交換時等に燃料集合体1aと共に弾性体33としてのコイルばねも交換することが望ましい。
The elastic body 33 is not limited to a coil spring, and a leaf spring or a bamboo spring may be used. Moreover, although the case where one coiled spring is used as the elastic body 33 is shown as an example in FIG.8 and FIG.9, the number of objects of the coiled spring as the elastic body 33 to install is not restricted to this, Two or more The coil spring may be installed. Further, in the present embodiment, one end (the upper end portion in the axial direction) of the coil spring as the elastic body 33 is fixed to the lower surface of the grid member 32a, but the present invention is not limited thereto. For example, one end (axially lower end) of the coil spring as the elastic body 33 is fixed to the upper surface of the handle 7a constituting the fuel assembly 1a, and the other end of the coil spring is not fixed to the lower surface of the grid member 32a. , And may be in contact with each other.
However, considering that the coil spring as the elastic body 33 is immersed in the cooling water (coolant) in the reactor pressure vessel 20 for a long time, one end of the coil spring as the elastic body 33 is on the upper surface of the handle 7a. It is desirable to fix and replace the coil assembly as the elastic member 33 together with the fuel assembly 1a at the time of refueling or the like.
 図10に、シュラウドヘッド25の近傍であって、図1に示す燃料浮き上がり防止部材31を設置した状態を示す。図10は、原子炉圧力容器20内の炉心21の上部の側面図である。炉心21は、三角格子状に稠密に配された燃料集合体1の最外周の側面、すなわち、最外周燃料集合体1の側面に、円環状(リング状)の炉心支持枠23を有する。炉心支持枠23の内側面(内周面)は、最外周燃料集合体1の形状(横断面が六角形状のチャンネルボックス5)と適合するよう凹凸を有する形状となっている。炉心支持枠23の外側面(外周面)は、円筒形状の炉心シュラウド24の内面(内周面)とほぼ同様の形状及び寸法を有している。炉心支持枠23は、炉心シュラウド24の内面(内周面)に設けた支持部(図示せず)に固定されている。図10に示すように、燃料浮き上がり防止部材31は、三角格子状に稠密に配された燃料集合体1を構成するハンドル7の上方に配されている。燃料浮き上がり防止部材31の最外周部は、炉心支持枠23にて支持されている。
これにより、燃料浮き上がり防止部材31は、炉心21内において水平方向及び鉛直方向(軸方向)のいずれの方向に対しても固定されている。なお、本実施例では、燃料浮き上がり防止部材31を炉心支持枠23にて支持する構成を一例として示すが、この構成に限られるものではない。例えば、炉心シュラウド24の内側面(内周面)に支持部材を設け、当該支持部材により、燃料浮き上がり防止部材31の最外周部を固定する構成としても良い。
FIG. 10 shows the vicinity of the shroud head 25 in which the fuel floating prevention member 31 shown in FIG. 1 is installed. FIG. 10 is a side view of the upper portion of the core 21 in the reactor pressure vessel 20. As shown in FIG. The core 21 has an annular (ring-like) core support frame 23 on the side of the outermost periphery of the fuel assembly 1 densely arranged in a triangular lattice, that is, the side of the outermost fuel assembly 1. The inner side surface (inner peripheral surface) of the core support frame 23 is shaped to have unevenness so as to match the shape of the outermost fuel assembly 1 (the channel box 5 having a hexagonal cross section). The outer surface (outer peripheral surface) of the core support frame 23 has substantially the same shape and size as the inner surface (inner peripheral surface) of the cylindrical core shroud 24. The core support frame 23 is fixed to a support (not shown) provided on the inner surface (inner peripheral surface) of the core shroud 24. As shown in FIG. 10, the fuel floating prevention member 31 is disposed above the handle 7 constituting the fuel assembly 1 densely arranged in the form of a triangular lattice. The outermost periphery of the fuel floating prevention member 31 is supported by the core support frame 23.
Thus, the fuel floating prevention member 31 is fixed in both the horizontal direction and the vertical direction (axial direction) in the core 21. In the present embodiment, a configuration in which the fuel floating prevention member 31 is supported by the core support frame 23 is shown as an example, but the present invention is not limited to this configuration. For example, a support member may be provided on the inner side surface (inner peripheral surface) of the core shroud 24, and the outermost periphery of the fuel floating prevention member 31 may be fixed by the support member.
 本実施例によれば、運転時における燃料浮き上がりを防止しつつ、定期検査或は燃料交換等の作業効率を向上し得る沸騰水型原子炉の炉心を提供することが可能となる。 
 また、本実施例によれば、Y字型の制御棒を囲むよう、相互に隣接して三角格子状に稠密に配される3体の燃料集合体のハンドル上面の長辺が、Y字型の制御棒の中心に向かうよう配されることから、原子炉運転時におけるハンドルの配置を変更することなく、定期検査或いは燃料交換等を実施でき、作業性を向上することが可能となる。 
 更にまた、本実施例によれば、Y字型の制御棒を囲むよう、相互に隣接して三角格子状に稠密に配される3体の燃料集合体のハンドル上面の長辺と交差するよう、三角格子の繰り返しパターン形状を備える格子部材を配することで、容易且つ単純な構造にて燃料浮き上がり防止部材を実現できる。 
 また、本実施例によれば、三角格子の繰り返しパターン形状を備える格子部材にばね等の弾性部材を配し燃料浮き上がり防止部材を構成することで、燃料集合体の軸方向上方への浮き上がりを好適に防止することが可能となる。
According to the present embodiment, it is possible to provide a core of a boiling water reactor capable of improving the working efficiency of periodic inspection or refueling while preventing fuel floating during operation.
Further, according to the present embodiment, the long sides of the upper surfaces of the handles of the three fuel assemblies closely arranged in the form of a triangular lattice adjacent to each other so as to surround the Y-shaped control rods are Y-shaped. Since the control rod is disposed to be directed to the center of the control rod, periodic inspection or refueling can be performed without changing the arrangement of the handle at the time of reactor operation, and the workability can be improved.
Furthermore, according to the present embodiment, the long sides of the upper surfaces of the handles of the three fuel assemblies closely arranged in the form of a triangular lattice adjacent to each other so as to surround the Y-shaped control rods are intersected. By arranging the grid member having the repeated pattern shape of the triangular grid, the fuel floating prevention member can be realized with a simple and simple structure.
Further, according to the present embodiment, by arranging an elastic member such as a spring on a grid member having a repeated pattern of triangular grids to constitute a fuel floating prevention member, it is preferable to lift the fuel assembly upward in the axial direction. It is possible to prevent
 図11は、本発明の他の実施例に係る実施例2の燃料浮き上がり防止部材の部分平面図と、そのD-D断面矢視図である。本実施例では、燃料集合体を構成するハンドルと嵌合し得る溝又は凹部を、燃料浮き上がり防止部材を構成する格子部材の下面に設けた点が実施例1と異なる。その他の構成は実施例1と同様であり、実施例1と同様の構成要素に同一符号を付し、以下では実施例1と重複する説明を省略する。 FIG. 11 is a partial plan view of a fuel lifting prevention member of a second embodiment according to another embodiment of the present invention, and a sectional view taken along the line DD of FIG. The present embodiment is different from the first embodiment in that a groove or a recess which can be fitted to a handle constituting the fuel assembly is provided on the lower surface of the lattice member constituting the fuel lifting prevention member. The other configuration is the same as that of the first embodiment. The same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
 図11の左図は、上述の実施例1において図7に示した構成と同様に、燃料浮き上がり防止部材31を構成する格子部材32の平面形状は、格子部材32a、格子部材32b、及び格子部材32cを三角格子状に組み合わせたものであり、それぞれの格子部材32a、格子部材32b、及び格子部材32cは、上述したように、燃料集合体1aのハンドル7a、燃料集合体1bのハンドル7b、及び燃料集合体1cのハンドル7cの上方に配される。また、図1にて説明したように、格子部材32aをハンドル7a上面の長辺71aに、格子部材32bをハンドル7b上面の長辺71bに、また、格子部材32cをハンドル7cの長辺71cに交差するよう、燃料浮き上がり防止部材31を構成する格子部材32を配する。 The left view of FIG. 11 has the same plan configuration of the grid member 32 constituting the fuel lift prevention member 31 as the grid member 32a, the grid member 32b, and the grid member similar to the configuration shown in FIG. 7 in the first embodiment described above. Each of the grid members 32a, 32b, and 32c, as described above, includes the handle 7a of the fuel assembly 1a and the handle 7b of the fuel assembly 1b, as described above. It is disposed above the handle 7c of the fuel assembly 1c. Also, as described in FIG. 1, the grid member 32a is on the long side 71a of the top surface of the handle 7a, the grid member 32b is on the long side 71b of the top surface of the handle 7b, and the grid member 32c is on the long side 71c of the handle 7c. A grid member 32 constituting the fuel lift prevention member 31 is disposed to intersect.
 図11の右図は、左図のD―D断面矢視図である。右図に示すように、燃料浮き上がり防止部材31を構成する格子部材32aの下面に、燃料集合体1のハンドル7の上面と交差する位置に、溝34(又は凹部)を設けている。 
 図12は、図11に示す燃料浮き上がり防止部材31を構成する格子部材32aとハンドル7aとの位置関係を示す部分平面図と、そのE―E断面矢視図であり、図13は、図11に示す燃料浮き上がり防止部材31を構成する格子部材32aとハンドルとの位置関係を示す部分平面図と、そのF―F断面矢視図である。
The right view of FIG. 11 is a sectional view taken along the line DD in the left view. As shown in the right figure, a groove 34 (or a recess) is provided on the lower surface of the lattice member 32a constituting the fuel lift prevention member 31 at a position intersecting the upper surface of the handle 7 of the fuel assembly 1.
12 is a partial plan view showing the positional relationship between the grid member 32a and the handle 7a constituting the fuel floating prevention member 31 shown in FIG. 11, and its EE cross section arrow view, and FIG. They are a partial plan view which shows the positional relationship of the grid member 32a which comprises the fuel floating prevention member 31 shown to, and a handle, and the FF cross section arrow directional view.
 図12の上図は、図1に示した燃料集合体1aと燃料浮き上がり防止部材31を構成する格子部材32aとの配置関係において、時計回り又は反時計回りに90度回転させた状態での部分平面図であり、図12の下図は、上図のE-E断面矢視図である。図12の上図に示すように、格子部材32aは、ハンドル7a上面の長辺と略直交するよう交差している。また、図12の下図に示すように、格子部材32aは、下面に略台形状の切り欠きを形成することにより得られる溝34(又は凹部)を有する。また、溝34(又は凹部)は、図13の下図に示すように、格子部材32aの幅方向(短辺方向)に連続している。
換言すれば、格子部材32aは、幅方向に連続する溝34(又は凹部)を備える。溝34(又は凹部)の底部、すなわち、図12の下図において、格子部材32aの上面に最も近い部分は、平坦化され弾性体33としてのコイルばねの一端が固定されている。このコイルばねの一端が固定された溝34(又は凹部)の底部より、ハンドル7a側に向かうに従い、溝34(又は凹部)の開口幅が緩やかに拡大するよう、ハンドル7a上面の短辺を挟みその両側に傾斜面を有する。このように、格子部材32aの下面に設けられた溝34(又は凹部)が傾斜面を有することから、燃料集合体1aを構成するハンドル7aに対し格子部材32aの位置決めが容易となる。より詳細には、三角格子の繰り返しパターン形状を有する燃料浮き上がり防止部材31を構成する格子部材32を、炉心21内に三角格子状に稠密に装荷される複数体の燃料集合体1の上方に配し、上述の図10に示すように、炉心支持枠23に固定する際において、格子部材32の下面に設けられた溝34(又は凹部)が傾斜面を有することから、燃料集合体1のハンドル7に対し上記傾斜面を介して、自己整合的に溝34(又は凹部)をハンドル7の上面に嵌合させることが可能となり、燃料集合体1を構成するハンドル7に対し格子部材32の位置決めが容易となる。
The upper view of FIG. 12 is a partial view of the fuel assembly 1a shown in FIG. 1 and the grid member 32a of the fuel lift preventing member 31 rotated 90 degrees clockwise or counterclockwise. FIG. 12 is a plan view, and the lower part of FIG. 12 is a sectional view taken along the line E-E in the upper view. As shown in the upper view of FIG. 12, the grid members 32a intersect so as to be substantially orthogonal to the long side of the upper surface of the handle 7a. Further, as shown in the lower part of FIG. 12, the grid member 32a has a groove 34 (or a recess) obtained by forming a substantially trapezoidal notch on the lower surface. Further, as shown in the lower part of FIG. 13, the groove 34 (or the recess) is continuous in the width direction (short side direction) of the grid member 32 a.
In other words, the grid member 32 a includes the groove 34 (or the recess) continuous in the width direction. The bottom of the groove 34 (or the recess), that is, the portion closest to the top surface of the grid member 32a in the lower part of FIG. 12, is flattened and one end of a coil spring as an elastic body 33 is fixed. The short side of the upper surface of the handle 7a is held so that the opening width of the groove 34 (or recess) gradually expands toward the handle 7a side from the bottom of the groove 34 (or recess) to which one end of the coil spring is fixed. It has slopes on both sides. Thus, since the groove 34 (or the recess) provided on the lower surface of the lattice member 32a has an inclined surface, the lattice member 32a can be easily positioned with respect to the handle 7a constituting the fuel assembly 1a. More specifically, the grid member 32 constituting the fuel lifting prevention member 31 having a repeated grid pattern of triangular grid is disposed above the plurality of fuel assemblies 1 densely loaded in the core 21 in the form of triangular grid. As shown in FIG. 10 described above, when fixed to the core support frame 23, the groove 34 (or the recess) provided on the lower surface of the lattice member 32 has an inclined surface. The groove 34 (or the recess) can be fitted on the upper surface of the handle 7 in a self-aligned manner through the inclined surface with respect to 7, and positioning of the grid member 32 with respect to the handle 7 constituting the fuel assembly 1 Becomes easy.
 また、図12の下図及び図13の下図に示すように、格子部材32aの下面に設けられた溝34(又は凹部)と、燃料集合体1aを構成するハンドル7aとが嵌合する。ここで、仮に、図12の上図に白抜き矢印にて示すA方向への変位、すなわち、格子部材32aの長辺方向(長手方向)に沿った、振動或いは外力が燃料集合体1aに付加された場合を想定する。図12の下図に示すように、ハンドル7aの長手方向に沿った2つの側面のうちいずれか一方が、格子部材32aの下面に設けられた溝34(又は凹部)の傾斜面と当接することにより、燃料集合体1aのA方向への変位が規制される。換言すれば、格子部材32aの下面に設けられた溝34(又は凹部)は、燃料集合体1の変位を規制する変位規制部としての機能を有する。なお、この変位規制部としての機能は、図11の左図において、白抜き矢印にて示す、B方向及びC方向の変位においても、それぞれ、燃料集合体1b及び燃料集合体1cの変位を、格子部材32b及び格子部材32cの下面に設けられた溝34(又は凹部)により規制される。上述のように、格子部材32の下面に設けられた溝34(又は凹部)が燃料集合体1の変位規制部として機能することにより、実施例1において図6に示した制御棒接触防止パッド12及び燃料集合体接触防止パッド13を、燃料集合体1を構成するチャンネルボックス5の側面に設けることが不要となる。換言すれば、格子部材32の下面に設けられた溝34(又は凹部)が燃料集合体1の変位規制部として機能することにより、相互に隣接して配される燃料集合体1間の間隙及び水平断面(横断面)Y字型の制御棒11の挿入路としての間隙を確保することが可能となる。 Further, as shown in the lower side of FIG. 12 and the lower side of FIG. 13, the groove 34 (or the recess) provided on the lower surface of the lattice member 32a is engaged with the handle 7a constituting the fuel assembly 1a. Here, temporarily, displacement in the A direction indicated by a white arrow in the upper drawing of FIG. 12, that is, vibration or external force along the long side direction (longitudinal direction) of the grid member 32a is applied to the fuel assembly 1a Assume that the As shown in the lower part of FIG. 12, one of the two side surfaces along the longitudinal direction of the handle 7a abuts on the inclined surface of the groove 34 (or the recess) provided on the lower surface of the grid member 32a. The displacement of the fuel assembly 1a in the A direction is restricted. In other words, the groove 34 (or the recess) provided on the lower surface of the grid member 32 a has a function as a displacement restricting portion that restricts the displacement of the fuel assembly 1. The function as the displacement restricting portion is the displacement of the fuel assembly 1b and the fuel assembly 1c also in the displacement in the B direction and the C direction indicated by white arrows in the left view of FIG. A groove 34 (or a recess) provided on the lower surface of the grid member 32 b and the grid member 32 c regulates the movement. As described above, the groove 34 (or the recess) provided on the lower surface of the grid member 32 functions as a displacement restricting portion of the fuel assembly 1, whereby the control rod contact preventing pad 12 shown in FIG. Also, it is not necessary to provide the fuel assembly contact prevention pad 13 on the side surface of the channel box 5 constituting the fuel assembly 1. In other words, the groove 34 (or the recess) provided on the lower surface of the grid member 32 functions as a displacement restricting portion of the fuel assembly 1 to make the gap between the fuel assemblies 1 disposed adjacent to each other It becomes possible to secure a gap as an insertion path of the control rod 11 of horizontal cross section (cross section) Y-shape.
 なお、格子部材32の下面に設けられる溝34(又は凹部)の開口幅は、嵌合するハンドル7の上面の幅(短辺)より大きければよく、開口幅は適宜設定すれば良い。 The opening width of the groove 34 (or the recess) provided on the lower surface of the grid member 32 may be larger than the width (short side) of the upper surface of the handle 7 to be fitted, and the opening width may be set appropriately.
 本実施例によれば、実施例1の効果に加え、燃料集合体を構成するハンドルに対し燃料浮き上がり防止部材を構成する格子部材の位置決めが容易となる。 
 また、本実施例によれば、燃料浮き上がり防止部材を構成する格子部材の下面に、燃料集合体を構成するハンドルと嵌合し得る溝(又は凹部)を有することから、燃料集合体の変位を規制することが可能となる。
According to the present embodiment, in addition to the effects of the first embodiment, the positioning of the grid member constituting the fuel floating prevention member with respect to the handle constituting the fuel assembly is facilitated.
Further, according to the present embodiment, since the lower surface of the grid member constituting the fuel lift prevention member has a groove (or a recess) which can be fitted to the handle constituting the fuel assembly, the fuel assembly can be displaced. It becomes possible to regulate.
 図14は、本発明の他の実施例に係る実施例3の燃料浮き上がり防止部材及び燃料集合体との配置関係を示す炉心の部分平面図であり、図15は、図14のG-G断面矢視図であって、燃料浮き上がり防止部材と燃料集合体の上部との位置関係を示す図である。本実施例では、燃料浮き上がり防止部材を構成する格子部材のうち、燃料集合体のハンドルと交差するよう配される格子部材の下面に、燃料集合体がY字型の制御棒側へと向かう変位を規制するための燃料集合体変位規制部を設けた点が実施例1と異なる。その他の構成は実施例1と同様であり、実施例1と同様の構成要素に同一符号を付し、以下では実施例1と重複する説明を省略する。 FIG. 14 is a partial plan view of the core showing the arrangement relationship between the fuel lift prevention member and the fuel assembly of Example 3 according to another example of the present invention, and FIG. 15 is a GG cross section of FIG. It is an arrow view, Comprising: It is a figure which shows the positional relationship of a fuel floating prevention member and the upper part of a fuel assembly. In this embodiment, of the grid members constituting the fuel lift prevention member, the fuel assemblies are displaced toward the Y-shaped control rod side on the lower surface of the grid members arranged to intersect with the fuel assembly handle. The second embodiment differs from the first embodiment in that a fuel assembly displacement restricting portion for restricting the pressure is provided. The other configuration is the same as that of the first embodiment. The same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
 図14に示すように、燃料浮き上がり防止部材31を構成する格子部材32のうち、格子部材32aは燃料集合体1aを構成するハンドル7a上面の長辺と交差するよう配されると共に、格子部材32bは燃料集合体1bを構成するハンドル7b上面の長辺と交差するよう配される。 
 図15に示すように、弾性体33としてのコイルばねの軸方向上端面が、格子部材32aの下面に固定され燃料浮き上がり防止部材31が構成される。この場合、燃料浮き上がり防止部材31を構成する弾性体33としてのコイルばねの軸方向下端面(弾性体33の格子部材32aの下面とは反対側の面)は、燃料集合体1aを構成するハンドル7aに固定されることなく、当接している。また、弾性体33としてのコイルばねの軸方向上端面が、格子部材32cの下面に固定され燃料浮き上がり防止部材31が構成される。この場合、燃料浮き上がり防止部材31を構成する弾性体33としてのコイルばねの軸方向下端面(弾性体33の格子部材32cの下面とは反対側の面)は、燃料集合体1cを構成するハンドル7caに固定されることなく、当接している。 
 格子部材32aの下面うち、弾性体33としてのコイルばねが固定される位置の近傍からY字型の制御棒11へと向かう領域に、燃料集合体1a側へ突出する凸部を有する。また、格子部材32cの下面うち、弾性体33としてのコイルばねが固定される位置の近傍からY字型の制御棒11へと向かう領域に、燃料集合体1c側へ突出する凸部を有する。
これら、格子部材32aの下面に設けられた凸部と格子部材32cの下面に設けられた凸部は、格子部材32a及び格子部材32cの接続部を介して連続し、燃料集合体変位規制部35を構成する。格子部材32a及び格子部材32cの接続部は、Y字型の制御棒11の中心であるタイロッド(またはセンタポスト)(図示せず)の直上に位置する。また、図15に示すように、格子部材32a及び格子部材32cの下面に設けられる燃料集合体変位規制部35のうち、格子部材32aの側の端面は、格子部材32aの下面より燃料集合体1a側へと向かうに従いY字型の制御棒11の中心側へと比較的急峻に傾斜する傾斜面を有する。また、燃料集合体変位規制部35のうち、格子部材32cの側の端面は、格子部材32cの下面より燃料集合体1c側へと向かうに従いY字型の制御棒11の中心側へと比較的急峻に傾斜する傾斜面を有する。
As shown in FIG. 14, of the lattice members 32 constituting the fuel lift-up preventing member 31, the lattice members 32a are arranged to intersect the long sides of the upper surface of the handle 7a constituting the fuel assembly 1a, and Are arranged to intersect with the long side of the upper surface of the handle 7b constituting the fuel assembly 1b.
As shown in FIG. 15, the axial direction upper end surface of the coil spring as the elastic body 33 is fixed to the lower surface of the lattice member 32a, and the fuel floating prevention member 31 is configured. In this case, the axial direction lower end surface (surface of the elastic member 33 opposite to the lower surface of the grid member 32a) of the coil spring as the elastic member 33 constituting the fuel floating prevention member 31 is a handle constituting the fuel assembly 1a. It is in contact without being fixed to 7a. Further, the axial direction upper end surface of the coil spring as the elastic body 33 is fixed to the lower surface of the lattice member 32c, and the fuel floating prevention member 31 is configured. In this case, the axial direction lower end surface of the coil spring as the elastic body 33 constituting the fuel floating prevention member 31 (the surface on the opposite side to the lower surface of the lattice member 32c of the elastic body 33) is a handle constituting the fuel assembly 1c. It is in contact without being fixed to 7ca.
In the lower surface of the grid member 32a, in the area from the vicinity of the position where the coil spring as the elastic body 33 is fixed to the Y-shaped control rod 11, there is provided a protrusion projecting toward the fuel assembly 1a. Further, in the lower surface of the grid member 32c, in the area from the vicinity of the position where the coil spring as the elastic body 33 is fixed to the Y-shaped control rod 11, there is provided a protrusion projecting toward the fuel assembly 1c.
The convex portion provided on the lower surface of the lattice member 32a and the convex portion provided on the lower surface of the lattice member 32c are continuous through the connection portion of the lattice member 32a and the lattice member 32c, and the fuel assembly displacement regulating portion 35 Configure The connection between the grid members 32a and 32c is located directly above the tie rod (or center post) (not shown) which is the center of the Y-shaped control rod 11. Further, as shown in FIG. 15, of the fuel assembly displacement restricting portions 35 provided on the lower surface of the lattice member 32a and the lattice member 32c, the end surface on the lattice member 32a side is the fuel assembly 1a from the lower surface of the lattice member 32a. It has an inclined surface which is relatively steeply inclined toward the center of the Y-shaped control rod 11 as it goes to the side. In the fuel assembly displacement restricting portion 35, the end face on the grid member 32c side is relatively toward the center of the Y-shaped control rod 11 as it goes from the lower surface of the grid member 32c to the fuel assembly 1c side. It has a steeply inclined slope.
 ここで、図14及び図15に白抜き矢印にて示すA方向及びC方向への変位、すなわち、格子部材32aの長辺方向(長手方向)に沿って、Y字型の制御棒11の中心側へと向かう水平方向の振動或いは外力が燃料集合体1aに付加され、格子部材32cの長辺方向(長手方向)に沿って、Y字型の制御棒11の中心側へと向かう水平方向の振動或いは外力が燃料集合体1cに付加された場合を想定する。この場合、図15に示すように、燃料集合体1aを構成するハンドル7aの長手方向に沿った2つの側面のうちY字型の制御棒11の中心側の側面が、燃料集合体変位規制部35の一方の端面である傾斜面と当接し、燃料集合体1aのA方向への変位が規制される。また、燃料集合体1cを構成するハンドル7cの長手方向に沿った2つの側面のうちY字型の制御棒11の中心側の側面が、燃料集合体変位規制部35の他方の端面である傾斜面と当接し、燃料集合体1cのC方向への変位が規制される。これにより、燃料集合体1a及び燃料集合体1c間に形成される間隙、すなわち、水平断面(横断面)Y字型の制御棒11の挿入路としての間隙を確保することが可能となる。よって、本実施例では、実施例1において図6に示した制御棒接触防止パッド12を、燃料集合体1を構成するチャンネルボックス5の側面に設けることが不要となる。 Here, the displacement in the A direction and the C direction indicated by the outlined arrows in FIGS. 14 and 15, that is, the center of the Y-shaped control rod 11 along the long side direction (longitudinal direction) of the grid member 32a. Horizontal vibration or external force toward the side is applied to the fuel assembly 1a, and the horizontal direction toward the center of the Y-shaped control rod 11 along the long side direction (longitudinal direction) of the grid member 32c. It is assumed that vibration or external force is applied to the fuel assembly 1c. In this case, as shown in FIG. 15, of the two side surfaces along the longitudinal direction of the handle 7a constituting the fuel assembly 1a, the side surface on the center side of the Y-shaped control rod 11 is the fuel assembly displacement restricting portion It abuts on the inclined surface which is one end face of 35, and the displacement of the fuel assembly 1a in the A direction is restricted. Further, of the two side surfaces along the longitudinal direction of the handle 7c constituting the fuel assembly 1c, the side surface on the center side of the Y-shaped control rod 11 is inclined at the other end surface of the fuel assembly displacement restricting portion 35. It abuts on the surface, and the displacement of the fuel assembly 1c in the C direction is restricted. As a result, it is possible to secure a gap formed between the fuel assembly 1a and the fuel assembly 1c, that is, a gap as an insertion path for the control rod 11 with a horizontal cross section (cross section) of Y-shape. Therefore, in the present embodiment, it is not necessary to provide the control rod contact prevention pad 12 shown in FIG. 6 in the first embodiment on the side surface of the channel box 5 constituting the fuel assembly 1.
 本実施例によれば、実施例1の効果に加え、燃料浮き上がり防止部材を構成する格子部材の下面に、燃料集合体変位規制部を有することから、燃料集合体のY字型の制御棒側への変位を規制することが可能となる。 According to the present embodiment, in addition to the effects of the first embodiment, the fuel assembly displacement restricting portion is provided on the lower surface of the lattice member constituting the fuel lift preventing member, so that the Y-shaped control rod side of the fuel assembly It is possible to regulate the displacement of the
 図16は、本発明の他の実施例に係る実施例4の燃料浮き上がり防止部材の部分平面図と、そのH―H断面矢視図及びI―I断面矢視図である。本実施例では、燃料浮き上がり防止部材を構成する格子部材のうち、ハンドルと交差する領域以外の領域における格子部材の下面の形状を、下方(燃料集合体側)に向かうに従い幅が小さくなる、すなわち、垂直断面形状が細くなるよう構成した点が実施例1と異なる。その他の構成は実施例1と同様であり、実施例1と同様の構成要素に同一符号を付し、以下では実施例1と重複する説明を省略する。 FIG. 16 is a partial plan view of a fuel floating prevention member according to a fourth embodiment of the present invention, and a sectional view taken along the line HH and a sectional view taken along the line I-I. In the present embodiment, of the lattice members constituting the fuel lift prevention member, the shape of the lower surface of the lattice member in the area other than the area intersecting with the handle decreases in width toward the lower side (the fuel assembly side). This embodiment differs from the first embodiment in that the vertical cross-sectional shape is configured to be thin. The other configuration is the same as that of the first embodiment. The same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
 図16の上図に示すように、燃料浮き上がり防止部材31を構成する格子部材32のうち、格子部材32aは燃料集合体1aを構成するハンドル7a上面の長辺と交差するよう配されると共に、格子部材32bは燃料集合体1bを構成するハンドル7b上面の長辺と交差するよう配され、格子部材32cは燃料集合体1cを構成するハンドル7c上面の長辺と交差するよう配される。 As shown in the upper drawing of FIG. 16, among the lattice members 32 constituting the fuel lift prevention member 31, the lattice members 32a are arranged to intersect the long side of the upper surface of the handle 7a constituting the fuel assembly 1a, The grid member 32b is disposed to intersect the long side of the top surface of the handle 7b constituting the fuel assembly 1b, and the grid member 32c is disposed to intersect the long side of the top surface of the handle 7c constituting the fuel assembly 1c.
 図16の左下図に示すように、上図における格子部材32aのH―H断面形状は、四角形状を成す。このH―H断面の位置が、燃料集合体1aを構成するハンドル7a上面の長辺と交差する位置に相当する。一方、図16の右下図に示すように、上図における格子部材32aのI―I断面形状は、下部側の形状が下方(燃料集合体側)へ向かうに従い幅が小さくなる、すなわち、垂直断面形状が細くなる形状を有する。このI―I断面の位置は、燃料集合体1aを構成するハンドル7a上面の長辺と交差しない位置に相当する。すなわち、本実施例の燃料浮き上がり防止部材31を構成する格子部材32は、燃料集合体1を構成するハンドル7と交差する領域においては、その垂直断面形状を四角形状とすることで、図示しない弾性体33としてのコイルばねの一端を固定し易い形状とすると共に、ハンドル7と交差しない領域においては垂直断面形状が、下部側において下方(燃料集合体側)へ向かうに従い幅が小さくなる、すなわち、垂直断面形状が細くなる形状とすることで、燃料集合体1内を上方へと通流する冷却水(冷却材)に対する圧損が低減される。
換言すれば、燃料浮き上がり防止部材31を構成する格子部材32のうち、燃料集合体1を構成するハンドル7と交差する領域以外の領域において、燃料集合体1の上部出口から流出する流体(冷却水)が格子部材32に衝突する際、格子部材32で受ける流体力を低減できる。これにより、燃料浮き上がり防止部材31の健全性を向上することが可能となる。
As shown in the lower left view of FIG. 16, the HH cross-sectional shape of the grid member 32a in the upper view forms a square shape. The position of the HH cross section corresponds to a position intersecting the long side of the upper surface of the handle 7a constituting the fuel assembly 1a. On the other hand, as shown in the lower right drawing of FIG. 16, the I-I cross-sectional shape of the grid member 32a in the upper drawing has a smaller width as the shape on the lower side goes downward (the fuel assembly side), ie, vertical cross-sectional shape Has a narrowing shape. The position of the I-I cross section corresponds to a position not intersecting the long side of the upper surface of the handle 7a constituting the fuel assembly 1a. That is, in the region intersecting with the handle 7 constituting the fuel assembly 1, the lattice member 32 constituting the fuel lift-up preventing member 31 of the present embodiment has a rectangular shape in vertical cross section to provide elasticity not shown. The end of the coil spring as the body 33 is shaped so as to be easily fixed, and the vertical cross-sectional shape in the area not intersecting with the handle 7 decreases in width toward the lower side (fuel assembly side) on the lower side, that is, vertical By making the cross-sectional shape thin, pressure loss to cooling water (coolant) flowing upward through the fuel assembly 1 is reduced.
In other words, the fluid flowing out from the upper outlet of the fuel assembly 1 (cooling water) in the region other than the region intersecting the handle 7 that constitutes the fuel assembly 1 among the grid members 32 that constitute the fuel floating prevention member 31 Can collide with the grid member 32, the fluid force received by the grid member 32 can be reduced. As a result, it is possible to improve the soundness of the fuel floating prevention member 31.
 本実施例によれば、実施例1の効果に加え、冷却水である流体の衝突による燃料浮き上がり防止部材が受ける流体力を低減でき、燃料浮き上がり防止部材の健全性の向上を図ることが可能となる。 According to the present embodiment, in addition to the effects of the first embodiment, it is possible to reduce the fluid force received by the fuel lift preventing member due to the collision of the fluid as the cooling water, and improve the soundness of the fuel lift preventing member. Become.
 図17は、本発明の他の実施例に係る実施例5の燃料浮き上がり防止部材及び燃料集合体との配置関係を示す炉心の部分平面図である。本実施例では、燃料浮き上がり防止部材を構成する各格子部材に、各燃料集合体を構成するハンドルの上面と対応して延伸する格子拡大部材を有する構成とした点が実施例1と異なる。その他の構成は実施例1と同様であり、実施例1と同様の構成要素に同一符号を付し、以下では実施例1と重複する説明を省略する。 FIG. 17 is a partial plan view of the core showing the arrangement relationship between the fuel uplift preventing member and the fuel assembly of a fifth embodiment according to another embodiment of the present invention. The present embodiment is different from the first embodiment in that each of the lattice members constituting the fuel floating prevention member has a lattice expanding member extending corresponding to the upper surface of the handle constituting each fuel assembly. The other configuration is the same as that of the first embodiment. The same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
 図17に示すように、燃料浮き上がり防止部材31を構成する格子部材32のうち、燃料集合体1aを構成するハンドル7a上面の長辺と交差するよう配される格子部材32aは、当該ハンドル7a上面の長辺と交差する位置に、ハンドル7aの上面に対応して延伸する格子拡大部材36aを有する。図17に示すように、格子拡大部材36aの平面の面積は、ハンドル7aの上面の面積以上である。格子部材32aと格子拡大部材36aは相互に直交する。また、燃料集合体1bを構成するハンドル7b上面の長辺と交差するよう配される格子部材32bは、当該ハンドル7b上面の長辺と交差する位置に、ハンドル7bの上面に対応して延伸する格子拡大部材36bを有する。格子拡大部材36bの平面の面積はハンドル7bの上面の面積以上であり、格子部材32bと格子拡大部材36bは相互に直交する。同様に、燃料集合体1cを構成するハンドル7c上面の長辺と交差するよう配される格子部材32cは、当該ハンドル7c上面の長辺と交差する位置に、ハンドル7cの上面に対応して延伸する格子拡大部材36cを有する。格子拡大部材36cの平面の面積はハンドル7cの上面の面積以上であり、格子部材32cと格子拡大部材36cは相互に直交する。 As shown in FIG. 17, among the lattice members 32 constituting the fuel floating prevention member 31, the lattice members 32a arranged to intersect the long side of the upper surface of the handle 7a constituting the fuel assembly 1a are the upper surfaces of the handle 7a. At a position intersecting the long side, a lattice expanding member 36a is extended corresponding to the upper surface of the handle 7a. As shown in FIG. 17, the area of the plane of the lattice expanding member 36a is equal to or larger than the area of the upper surface of the handle 7a. The grid member 32a and the grid expanding member 36a are orthogonal to each other. Further, a grid member 32b arranged to intersect the long side of the upper surface of the handle 7b constituting the fuel assembly 1b extends at a position intersecting the long side of the upper surface of the handle 7b in correspondence with the upper surface of the handle 7b. It has a lattice expanding member 36b. The area of the plane of the lattice expanding member 36b is equal to or larger than the area of the upper surface of the handle 7b, and the lattice member 32b and the lattice expanding member 36b are orthogonal to each other. Similarly, a grid member 32c arranged to intersect the long side of the upper surface of the handle 7c constituting the fuel assembly 1c extends in a position corresponding to the upper surface of the handle 7c at a position intersecting the long side of the upper surface of the handle 7c. Grating expanding member 36c. The area of the plane of the lattice expanding member 36c is equal to or larger than the area of the upper surface of the handle 7c, and the lattice member 32c and the lattice expanding member 36c are orthogonal to each other.
 図18は、図17に示す燃料浮き上がり防止部材31を構成する格子部材32a及び格子拡大部材36a並びにハンドル7aとの位置関係を示す部分平面図とそのJ―J断面矢視図であり、図19は、図17に示す燃料浮き上がり防止部材31を構成する格子部材32a及び格子拡大部材36a並びにハンドル7aとの位置関係を示す部分平面図と、そのK―K断面矢視図である。 
 図18の上図は、図17に示した燃料集合体1aと燃料浮き上がり防止部材31を構成する格子部材32aとの配置関係において、時計回り又は反時計回りに90度回転させた状態での部分平面図であり、図18の下図は、上図のJ―J断面矢視図である。図18の上図に示すように、格子拡大部材36aは、燃料集合体1aを構成するハンドル7aの上面と同等の長さ及び同等の幅を有する。弾性体33としてのコイルばねの一端は、格子拡大部材36aの下面に固定され、弾性体33としてのコイルばねの一端はハンドル7aに固定されることなく、当接している。
18 is a partial plan view showing the positional relationship between the lattice member 32a, the lattice expanding member 36a and the handle 7a constituting the fuel floating prevention member 31 shown in FIG. 17 and its JJ cross section arrow view; 17 is a partial plan view showing a positional relationship between a grid member 32a, a lattice expanding member 36a, and a handle 7a constituting the fuel floating prevention member 31 shown in FIG. 17, and its K-K cross section arrow view.
The upper view of FIG. 18 is a portion in a state of being rotated 90 degrees clockwise or counterclockwise in the arrangement relationship between the fuel assembly 1a shown in FIG. 17 and the lattice member 32a constituting the fuel floating prevention member 31. FIG. 18 is a plan view, and the lower part of FIG. 18 is a sectional view taken along the line JJ in the upper view. As shown in the upper part of FIG. 18, the lattice expanding member 36a has the same length and the same width as the upper surface of the handle 7a constituting the fuel assembly 1a. One end of a coil spring as the elastic body 33 is fixed to the lower surface of the lattice expanding member 36a, and one end of the coil spring as the elastic body 33 is in contact with the handle 7a without being fixed.
 図19の上図は、図17に示した燃料集合体1aと、格子部材32a及び格子拡大部材36aとの配置関係と同様であり、図19の下図は、K―K断面矢視図である。図19の下図に示すように、格子拡大部材36aの下面に、長手方向に沿って相互に離間し、一端が固定される2つの弾性体33としてのコイルばねを備える。2つの弾性体33としてのコイルばねの他端は固定されることなく、ハンドル7aの上面と当接している。このように、格子拡大部材36aにて、ハンドル7aの上面全面にて、燃料集合体1aの軸方向上への浮き上がりを防止できる。なお、図19の下図に示すように、格子拡大部材36aを有することにより、弾性体33としてのコイルばねを複数配することが可能となり、1つ当たりのコイルばね(弾性体33)への負荷を低減することも可能となる。 The upper view of FIG. 19 is the same as the arrangement relationship between the fuel assembly 1a shown in FIG. 17 and the lattice member 32a and the lattice expanding member 36a, and the lower view of FIG. . As shown in the lower part of FIG. 19, coil springs as two elastic bodies 33 are provided on the lower surface of the lattice expanding member 36 a so as to be mutually separated along the longitudinal direction and to be fixed at one end. The other ends of the coil springs as the two elastic bodies 33 are in contact with the upper surface of the handle 7a without being fixed. Thus, floating of the fuel assembly 1a in the axial direction can be prevented by the lattice expanding member 36a on the entire top surface of the handle 7a. Incidentally, as shown in the lower part of FIG. 19, by providing the lattice expanding member 36a, it becomes possible to arrange a plurality of coil springs as the elastic body 33, and a load on the coil spring (elastic body 33) per one It is also possible to reduce the
 本実施例によれば、実施例1による効果に加え、燃料浮き上がり防止部材を構成する各格子部材に格子拡大部材を備えることで、より効果的に燃料集合体の浮き上がりを防止することができる。 
 また、本実施例によれば、燃料浮き上がり防止部材及び/又は燃料集合体が損傷することを防止すために配される弾性体の負荷を低減でき、弾性体の長寿命化を図ることが可能となる。
According to this embodiment, in addition to the effects of the first embodiment, by providing the lattice expanding members to the respective lattice members constituting the fuel floating prevention member, floating of the fuel assembly can be more effectively prevented.
Moreover, according to the present embodiment, the load on the elastic body disposed to prevent damage to the fuel floating prevention member and / or the fuel assembly can be reduced, and the life of the elastic body can be prolonged. It becomes.
 図20は、本発明の他の実施例に係る実施例6の燃料浮き上がり防止部材及び燃料集合体との配置関係を示す炉心の部分平面図である。本実施例では、燃料集合体を構成するハンドル上面の短辺(ハンドルの長手方向の両端部を画定する辺)がY字型の制御棒の中心であるタイロッド(またはセンタポスト)を向くよう燃料集合体を炉心に装荷すると共に、複数の格子部材の接続部がハンドル上面の長辺と交差するよう燃料浮き上がり防止部材を構成する格子部材を配する点が実施例1と異なる。その他の構成は実施例1と同様であり、実施例1と同様の構成要素に同一符号を付し、以下では実施例1と重複する説明を省略する。 FIG. 20 is a partial plan view of the core showing the arrangement relationship between the fuel uplift preventing member and the fuel assembly of a sixth embodiment according to another embodiment of the present invention. In this embodiment, the short sides of the upper surface of the handle constituting the fuel assembly (the sides defining the longitudinal ends of the handle) are directed to the tie rod (or center post) which is the center of the Y-shaped control rod. The embodiment differs from the first embodiment in that the assembly is loaded in the core, and the grid members constituting the fuel floating prevention member are arranged such that the connection portions of the plurality of grid members intersect the long side of the upper surface of the handle. The other configuration is the same as that of the first embodiment. The same components as those of the first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated.
 図20に示すように、相互に隣接し三角格子状に稠密に配される燃料集合体1a、燃料集合体1b、及び燃料集合体1cの間に水平断面(横断面)がY字型の制御棒11が配されている。燃料集合体1aを構成するハンドル7a上面の短辺72a(ハンドル7aの長手方向に沿った両側面を画定する辺)、燃料集合体1bを構成するハンドル7b上面の短辺72b(ハンドル7bの長手方向に沿った両側面を画定する辺)、及び燃料集合体1cを構成するハンドル7c上面の短辺72c(ハンドル7cの長手方向に沿った両側面を画定する辺)は、Y字型の制御棒11の中心であるタイロッド(またはセンタポスト)(図示せず)に向かうよう配されている。このような配置関係は、相互に隣接して三角格子状に配される他の3体の燃料集合体と、これら3体の燃料集合体1間にY字型の制御棒11が配される場合においても同様である。このように、水平断面(横断面)がY字型の制御棒11を囲むよう、相互に隣接して三角格子状に稠密に配される3体の燃料集合体1a~1cのハンドル7a~7c上面の短辺72a~72cの全てが、水平断面(横断面)がY字型の制御棒11の中心であるタイロッド(またはセンタポスト)に向くよう配されることから、原子炉運転時におけるハンドル7a~7cの配置を変更することなく、定期検査或いは燃料交換等を実施でき、作業性を向上することが可能となる。 As shown in FIG. 20, control of a Y-shaped horizontal cross section (cross section) between the fuel assembly 1a, the fuel assembly 1b, and the fuel assembly 1c closely arranged in the form of a triangular lattice adjacent to each other A bar 11 is arranged. Short side 72a of the upper surface of the handle 7a constituting the fuel assembly 1a (side defining both side surfaces along the longitudinal direction of the handle 7a), short side 72b of the upper surface of the handle 7b constituting the fuel assembly 1b (long side of the handle 7b Y-shaped control is a side that defines both sides along the direction, and a short side 72c of the top surface of the handle 7c that constitutes the fuel assembly 1c (a side that defines the two sides along the longitudinal direction of the handle 7c) It is arranged to be directed to a tie rod (or center post) (not shown) which is the center of the rod 11. Such an arrangement relationship is such that Y-shaped control rods 11 are disposed between the three other fuel assemblies disposed adjacent to each other in a triangular lattice and the three fuel assemblies 1. The same is true for cases. Thus, the handles 7a to 7c of the three fuel assemblies 1a to 1c closely arranged in the form of a triangular lattice adjacent to each other so that the horizontal cross section (cross section) surrounds the Y-shaped control rod 11 Since all the short sides 72a to 72c of the top face are directed to the tie rod (or center post) which is the center of the Y-shaped control rod 11, the handle during reactor operation The periodic inspection or the fuel replacement can be performed without changing the arrangement of 7a to 7c, and the workability can be improved.
 また、図20に示すように、燃料浮き上がり防止部材31を構成する格子部材32は、三角格子の繰り返しパターン形状を備える。例えば、燃料集合体1aのハンドル7aの上方に配される格子部材32は、ハンドル7a上面の長辺71a(ハンドル7aの長手方向に沿った両側面を画定する辺)と略直交するよう長辺71aの略中央部に配される格子部材32a、長辺71aの略中央部にて長辺71aに対し所定の傾斜角にて交差する格子部材32d、及び長辺71aの略中央部にて長辺71aに対し所定の傾斜角にて交差する格子部材32eを有する。換言すれば、格子部材32a、格子部材32d、及び格子部材32eの接続部が長辺71aの略中央部上方に位置する。格子部材32a、格子部材32d、及び格子部材32eの接続部の下面に一端が固定され、他端がハンドル7aの上面に固定されることなく当接する弾性体33としてのコイルばね(図示せず)が設けられている。 Moreover, as shown in FIG. 20, the lattice member 32 which comprises the fuel floating prevention member 31 is provided with the repeating pattern shape of a triangular lattice. For example, the grid member 32 disposed above the handle 7a of the fuel assembly 1a has a long side so as to be substantially orthogonal to the long side 71a of the upper surface of the handle 7a (a side defining both side surfaces along the longitudinal direction of the handle 7a) A grid member 32a disposed substantially at the center of 71a, a grid member 32d intersecting at a predetermined inclination angle with the long side 71a at a substantially center of the long side 71a, and a length substantially at the center of the long side 71a The grid member 32e intersects the side 71a at a predetermined inclination angle. In other words, the connection portion of the grid member 32a, the grid member 32d, and the grid member 32e is located above the substantially central portion of the long side 71a. A coil spring (not shown) as an elastic body 33 having one end fixed to the lower surface of the connecting portion of the grid members 32a, 32d and 32e and the other end abutting without being fixed to the upper surface of the handle 7a Is provided.
 上述の関係は、他の相互に隣接して三角格子状に配される3体の燃料集合体1と、これら3体の燃料集合体1の上方に配される格子部材32についても同様である。このように、各燃料集合体1は、3本の格子部材の接続部にて浮き上がりが防止されることから、格子部材32により構成される燃料浮き上がり防止部材31の健全性が向上される。 The above-mentioned relationship is similarly applied to the three fuel assemblies 1 adjacent to each other in the form of a triangular lattice and the lattice members 32 disposed above the three fuel assemblies 1. . As described above, each fuel assembly 1 is prevented from rising at the connection portion of the three lattice members, so that the soundness of the fuel floating prevention member 31 configured by the lattice members 32 is improved.
 なお、3本の格子部材の接続部の下面の形状は、上述の実施例1(図8、図9)又は実施例2(図12、図13)と同様の形状とすれば良く、また、実施例5に示した格子拡大部材(図17~図19)を備える構成としても良い。更には、格子部材において接続部以外の領域の下面の形状を上述の実施例4に示した形状(図16の右下図)としても良い。 In addition, the shape of the lower surface of the connection portion of the three grid members may be the same as that of the first embodiment (FIGS. 8 and 9) or the second embodiment (FIGS. 12 and 13) described above. The lattice expanding member (FIGS. 17 to 19) shown in the fifth embodiment may be provided. Furthermore, in the grid member, the shape of the lower surface of the region other than the connection portion may be the shape shown in the above-described fourth embodiment (lower right view in FIG. 16).
 本実施例によれば、実施例1の効果に加え、燃料浮き上がり防止部材を構成する複数本の格子部材の接続部にて、燃料集合体の浮き上がりが防止されることから、燃料浮き上がり防止部材の健全性を更に向上することが可能となる。 According to the present embodiment, in addition to the effects of the first embodiment, since the fuel assembly is prevented from floating at the connection portion of the plurality of grid members constituting the fuel floating prevention member, the fuel floating prevention member It is possible to further improve the soundness.
 なお、上述の実施例1~実施例6では、沸騰水型原子炉の一例として、資源再利用型沸騰水型原子炉(RBWR)を示したが、これに限られるものではなく、水平断面が六角形状のチャンネルボックスを有する燃料集合体を、相互に隣接して三角格子状に稠密に装荷する炉心構造であれば、例えば、改良型沸騰水型原子炉(ABWR)、高経済性単純化沸騰水型原子炉(ESBWR)、或いは再循環ポンプを有する通常の沸騰水型原子炉(BWR)にも同様に適用できる。 In Examples 1 to 6 described above, although a resource recycling type boiling water reactor (RBWR) is shown as an example of a boiling water reactor, the present invention is not limited to this, and the horizontal cross section is not limited to this. If it is a core structure in which fuel assemblies having hexagonal channel boxes are densely loaded adjacent to each other in a triangular lattice, for example, an improved boiling water reactor (ABWR), highly economical simplified boiling It is equally applicable to a water reactor (ESBWR) or a conventional boiling water reactor (BWR) having a recirculation pump.
 また、上述の実施例2~実施例5に示した構成を、任意の組み合わせにて沸騰水型原子炉を構成しても良い。例えば、実施例2と実施例3とを組み合わせ、格子部材32の下面に溝34(又は凹部)及び燃料集合体変位規制部35を備える構成としても良い。また、実施例2と実施例4とを組み合わせ、格子部材32の下面であってハンドルと交差する領域に溝34(又は凹部)を設け、ハンドルと交差する領域以外の領域における格子部材32の下面の形状を垂直断面形状が細くする構成としても良い。また、実施例2~実施例5の構成を全て組み合わせても良く、すなわち、実施例2~実施例5のうち、2つ以上の実施例を任意に組み合わせても良い。 In addition, the boiling water nuclear reactor may be configured by combining the configurations shown in the above-mentioned Example 2 to Example 5 in any combination. For example, the groove 34 (or the recess) and the fuel assembly displacement restricting portion 35 may be provided on the lower surface of the lattice member 32 by combining the second embodiment and the third embodiment. Further, the second embodiment and the fourth embodiment are combined, and a groove 34 (or a recess) is provided on the lower surface of the grid member 32 in the area intersecting the handle, and the lower surface of the grid member 32 in the area other than the area intersecting the handle. The vertical cross-sectional shape may be configured to be thin. Further, all the configurations of the embodiment 2 to the embodiment 5 may be combined, that is, two or more embodiments of the embodiment 2 to the embodiment 5 may be arbitrarily combined.
 なお、本発明は上記した実施例に限定されるものではなく、様々な変形例が含まれる。
例えば、上記した実施例は本発明を分かりやすく説明するために詳細に説明したものであり、必ずしも説明した全ての構成を備えるものに限定されるものではない。
The present invention is not limited to the embodiments described above, but includes various modifications.
For example, the embodiments described above are described in detail in order to explain the present invention in an easy-to-understand manner, and are not necessarily limited to those having all the configurations described.
1,1a,1b,1c・・・燃料集合体,2・・・燃料棒,3・・・上部タイプレート,4・・・下部タイプレート,5・・・チャンネルボックス,6・・・燃料スペーサ,7,7a,7b,7c・・・ハンドル,8・・・燃料支持金具,9・・・上部開口部,10・・・制御棒移動用開口部,11・・・制御棒,12・・・制御棒接触防止パッド,13・・・燃料集合体接触防止パッド,14・・・インターナルポンプ,20・・・原子炉圧力容器,21・・・炉心,22・・・炉心支持板,23・・・炉心支持枠,24・・・炉心シュラウド,25・・・シュラウドヘッド,26・・・ダウンカマ,27・・・気水分離器,28・・・蒸気乾燥器,29a・・・主蒸気配管,29b・・・給水配管,30・・・下部プレナム,31・・・燃料浮き上がり防止部材,32,32a,32b,32c,32d,32e・・・格子部材,33・・・弾性体,34・・・溝,35・・・燃料集合体変位規制部,36a,36b,36c,36d,36e・・・格子拡大部材,71a,71b,71c・・・長辺,72a,72b,72c・・・短辺 1, 1a, 1b, 1c: fuel assembly, 2: fuel rod 3, upper tie plate 4, lower tie plate 5, channel box 6, fuel spacer , 7, 7a, 7b, 7c ... handle, 8 ... fuel support bracket, 9 ... top opening, 10 ... opening for control rod movement, 11 ... control rod, 12 · · · Control rod contact preventing pad 13, fuel assembly contact preventing pad 14, internal pump 20, reactor pressure vessel 21, core 22, core support plate 23,・ ・ ・ Core support frame, 24 ・ ・ ・ Core shroud, 25 ・ ・ ・ Shroud head, 26 ・ ・ ・ down link, 27 ・ ・ ・ Air-water separator, 28 ・ ・ ・ Steam dryer, 29a · · · Main steam Piping, 29b ··· Water supply piping, 30 · · · Lower plenum, 31 · · · Fuel lifting preventing members 32, 32a, 32b, 32c, 32d, 32e: lattice members, 33: elastic bodies, 34: grooves, 35: fuel assembly displacement regulating portion, 36a, 36b, 36c, 36d, 36e ... lattice expanding members, 71a, 71b, 71c ... long sides, 72a, 72b, 72c ... short sides

Claims (15)

  1.  燃料集合体が三角格子状配列で稠密に配置され、3体の燃料集合体の中心に水平断面Y字型の制御棒が挿入される沸騰水型原子炉の炉心であって、
     前記燃料集合体は、前記水平断面Y字型の制御棒を囲む3体の燃料集合体に設けられるハンドルの上面の長辺又は短辺が、前記水平断面Y字型の制御棒の中心に向くように配され、
     前記ハンドルの上面の上方に配され、前記燃料集合体の上方への浮き上がりを抑制する燃料浮き上がり防止部材を備えることを特徴とする沸騰水型原子炉の炉心。
    A core of a boiling water nuclear reactor, in which fuel assemblies are densely arranged in a triangular lattice arrangement, and control rods with a horizontal cross section Y-shape are inserted at the centers of three fuel assemblies,
    In the fuel assembly, the long side or the short side of the upper surface of the handle provided on the three fuel assemblies surrounding the control rod with the horizontal cross section Y-shape faces the center of the control rod with the horizontal cross section Y-shaped Arranged as
    A core of a boiling water nuclear reactor, comprising: a fuel floating prevention member disposed above the upper surface of the handle and suppressing upward floating of the fuel assembly.
  2.  請求項1に記載の沸騰水型原子炉の炉心において、
     前記燃料浮き上がり防止部材は、三角格子の繰り返しパターン形状を有する格子部材を備えることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 1,
    The core of a boiling water nuclear reactor, wherein the fuel lifting prevention member comprises a grid member having a repeating pattern shape of a triangular grid.
  3.  請求項2に記載の沸騰水型原子炉の炉心において、
     前記ハンドルの上面の長辺と交差する前記格子部材と、前記ハンドルの上面との間に弾性体を設け、前記弾性体の一端が前記ハンドルの上面の長辺と交差する前記格子部材の下面又は前記ハンドルの上面に固定されることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 2,
    An elastic body is provided between the grid member intersecting the long side of the upper surface of the handle, and the upper surface of the handle, and the lower surface of the grid member where one end of the elastic body intersects the long side of the upper surface of the handle A core of a boiling water reactor, which is fixed to an upper surface of the handle.
  4.  請求項3に記載の沸騰水型原子炉の炉心において、
     前記弾性体は、コイルばね、板ばね、又は竹の子ばねであり、前記燃料集合体を下方へ押圧することを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 3,
    The core of a boiling water reactor, wherein the elastic body is a coil spring, a leaf spring, or a bamboo spring, and presses the fuel assembly downward.
  5.  請求項3に記載の沸騰水型原子炉の炉心において、
     前記格子部材の下面であって、前記ハンドルの上面の長辺と交差する部分に溝又は凹部を備え、前記溝又は凹部の開口幅は前記ハンドルの上面の幅よりも大きく、前記ハンドルの上面が前記弾性体を介して前記溝又は凹部に嵌合することを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 3,
    The lower surface of the grid member is provided with a groove or recess in a portion intersecting the long side of the upper surface of the handle, the opening width of the groove or recess is larger than the width of the upper surface of the handle, and the upper surface of the handle is A core of a boiling water reactor, which is fitted to the groove or the recess through the elastic body.
  6.  請求項3に記載の沸騰水型原子炉の炉心において、
     前記格子部材の下面であって、前記ハンドルの上面の長辺と交差する部分のうち前記水平断面Y字型の制御棒の中心側から、前記水平断面Y字型の制御棒の中心へと向かう領域に、燃料集合体側へ突出する凸部を有し、前記凸部に前記ハンドルが当接することにより前記燃料集合体が前記水平断面Y字型の制御棒の中心へと向かう変位を規制する燃料集合体変位規制部を備えることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 3,
    From the center side of the control rod of the horizontal cross section Y-shape to the center of the control rod of the horizontal cross section Y-shape from the center side of the control rod of the horizontal cross section Y shape in the lower surface of the grid member The region has a convex portion projecting toward the fuel assembly side, and the fuel assembly restricts the displacement toward the center of the control rod of the horizontal cross section Y shape by abutting the handle to the convex portion. A core of a boiling water reactor comprising an assembly displacement control unit.
  7.  請求項3に記載の沸騰水型原子炉の炉心において、
     前記格子部材の下面であって、前記ハンドルの上面の長辺と交差する部分以外の領域における垂直断面形状が前記燃料集合体側へ向かうに従い細くなることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 3,
    A core of a boiling water reactor, wherein a vertical cross-sectional shape in a region other than a portion which is a lower surface of the grid member and intersects with a long side of an upper surface of the handle becomes thinner toward the fuel assembly.
  8.  請求項3に記載の沸騰水型原子炉の炉心において、
     前記格子部材は、前記ハンドルの上面の長辺と交差する部分に前記ハンドルの上面の長辺に対応して延伸する格子拡大部材を有し、前記格子拡大部材の下面と前記ハンドルの上面との間に前記弾性体が配されることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 3,
    The grid member has a grid expanding member extending corresponding to the long side of the upper surface of the handle at a portion intersecting the long side of the upper surface of the handle, and the lower surface of the grid expanding member and the upper surface of the handle A core of a boiling water reactor, wherein the elastic body is disposed therebetween.
  9.  請求項3に記載の沸騰水型原子炉の炉心において、
     三角格子を形成する複数の格子部材の接続部が、前記ハンドルの上面の略中央部の上方に位置し、前記複数の格子部材の接続部の下面と前記ハンドルの上面の略中央部との間に前記弾性体が配されることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 3,
    A connection portion of a plurality of grid members forming a triangular grid is located above a substantially central portion of the upper surface of the handle, and between a lower surface of the connection portion of the plurality of grid members and a substantially central portion of the upper surface of the handle A core of a boiling water reactor, characterized in that the elastic body is disposed.
  10.  請求項5乃至請求項7のうち、いずれか1項に記載の沸騰水型原子炉の炉心において、 前記格子部材は、前記ハンドルの上面の長辺と交差する部分に前記ハンドルの上面の長辺に対応して延伸する格子拡大部材を有し、前記格子拡大部材の下面と前記ハンドルの上面との間に前記弾性体が配されることを特徴とする沸騰水型原子炉の炉心。 The core of the boiling water reactor according to any one of claims 5 to 7, wherein the grid member is a long side of the upper surface of the handle at a portion intersecting with the long side of the upper surface of the handle. A core of a boiling water reactor, comprising: a lattice expansion member extending corresponding to the elastic body disposed between the lower surface of the lattice expansion member and the upper surface of the handle.
  11.  請求項5又は請求項6に記載の沸騰水型原子炉の炉心において、
     前記格子部材の下面であって、前記ハンドルの上面の長辺と交差する部分以外の領域における垂直断面形状が前記燃料集合体側へ向かうに従い細くなることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 5 or 6,
    A core of a boiling water reactor, wherein a vertical cross-sectional shape in a region other than a portion which is a lower surface of the grid member and intersects with a long side of an upper surface of the handle becomes thinner toward the fuel assembly.
  12.  請求項5に記載の沸騰水型原子炉の炉心において、
     前記格子部材の下面であって、前記ハンドルの上面の長辺と交差する部分のうち前記水平断面Y字型の制御棒の中心側から、前記水平断面Y字型の制御棒の中心へと向かう領域に、燃料集合体側へ突出する凸部を有し、前記凸部に前記ハンドルが当接することにより前記燃料集合体が前記水平断面Y字型の制御棒の中心へと向かう変位を規制する燃料集合体変位規制部を備えることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 5,
    From the center side of the control rod of the horizontal cross section Y-shape to the center of the control rod of the horizontal cross section Y-shape from the center side of the control rod of the horizontal cross section Y shape in the lower surface of the grid member The region has a convex portion projecting toward the fuel assembly side, and the fuel assembly restricts the displacement toward the center of the control rod of the horizontal cross section Y shape by abutting the handle to the convex portion. A core of a boiling water reactor comprising an assembly displacement control unit.
  13.  請求項12に記載の沸騰水型原子炉の炉心において、
     前記格子部材は、前記ハンドルの上面の長辺と交差する部分に前記ハンドルの上面の長辺に対応して延伸する格子拡大部材を有し、前記格子拡大部材の下面と前記ハンドルの上面との間に前記弾性体が配されることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 12,
    The grid member has a grid expanding member extending corresponding to the long side of the upper surface of the handle at a portion intersecting the long side of the upper surface of the handle, and the lower surface of the grid expanding member and the upper surface of the handle A core of a boiling water reactor, wherein the elastic body is disposed therebetween.
  14.  請求項13に記載の沸騰水型原子炉の炉心において、
     前記格子部材は、前記ハンドルの上面の長辺と交差する部分に前記ハンドルの上面の長辺に対応して延伸する格子拡大部材を有し、前記格子拡大部材の下面と前記ハンドルの上面との間に前記弾性体が配されることを特徴とする沸騰水型原子炉の炉心。
    In a core of a boiling water reactor according to claim 13,
    The grid member has a grid expanding member extending corresponding to the long side of the upper surface of the handle at a portion intersecting the long side of the upper surface of the handle, and the lower surface of the grid expanding member and the upper surface of the handle A core of a boiling water reactor, wherein the elastic body is disposed therebetween.
  15.  請求項5乃至請求項8のうち、いずれか1項に記載の沸騰水型原子炉の炉心において、 前記燃料浮き上がり防止部材の最外周部は、内周面に最外周に装荷される燃料集合体と適合する形状を有すると共に炉心の外周に設けられる円環状の炉心支持枠、又は、円筒形状の炉心シュラウドの内周面に設けられる支持部材に固定されることを特徴とする沸騰水型原子炉の炉心。 The core of the boiling water reactor according to any one of claims 5 to 8, wherein the outermost periphery of the fuel floating preventing member is loaded on the inner peripheral surface at the outermost periphery. The boiling water reactor is characterized in that it is fixed to a toroidal core support frame provided on the outer periphery of the core, or a support member provided on the inner peripheral surface of the cylindrical core shroud, having a shape compatible with the above. Core.
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