WO2016084146A1 - 原子炉燃料棒およびそれを束ねた燃料集合体 - Google Patents
原子炉燃料棒およびそれを束ねた燃料集合体 Download PDFInfo
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- WO2016084146A1 WO2016084146A1 PCT/JP2014/081175 JP2014081175W WO2016084146A1 WO 2016084146 A1 WO2016084146 A1 WO 2016084146A1 JP 2014081175 W JP2014081175 W JP 2014081175W WO 2016084146 A1 WO2016084146 A1 WO 2016084146A1
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- fuel
- fuel rod
- cladding tube
- silicon carbide
- reactor
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K1/00—Soldering, e.g. brazing, or unsoldering
- B23K1/0008—Soldering, e.g. brazing, or unsoldering specially adapted for particular articles or work
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- B—PERFORMING OPERATIONS; TRANSPORTING
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- B23K1/00—Soldering, e.g. brazing, or unsoldering
- B23K1/14—Soldering, e.g. brazing, or unsoldering specially adapted for soldering seams
- B23K1/18—Soldering, e.g. brazing, or unsoldering specially adapted for soldering seams circumferential seams, e.g. of shells
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- B23K1/00—Soldering, e.g. brazing, or unsoldering
- B23K1/19—Soldering, e.g. brazing, or unsoldering taking account of the properties of the materials to be soldered
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- B23K20/00—Non-electric welding by applying impact or other pressure, with or without the application of heat, e.g. cladding or plating
- B23K20/02—Non-electric welding by applying impact or other pressure, with or without the application of heat, e.g. cladding or plating by means of a press ; Diffusion bonding
- B23K20/023—Thermo-compression bonding
- B23K20/026—Thermo-compression bonding with diffusion of soldering material
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- B23K20/00—Non-electric welding by applying impact or other pressure, with or without the application of heat, e.g. cladding or plating
- B23K20/16—Non-electric welding by applying impact or other pressure, with or without the application of heat, e.g. cladding or plating with interposition of special material to facilitate connection of the parts, e.g. material for absorbing or producing gas
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- B23K20/00—Non-electric welding by applying impact or other pressure, with or without the application of heat, e.g. cladding or plating
- B23K20/22—Non-electric welding by applying impact or other pressure, with or without the application of heat, e.g. cladding or plating taking account of the properties of the materials to be welded
- B23K20/233—Non-electric welding by applying impact or other pressure, with or without the application of heat, e.g. cladding or plating taking account of the properties of the materials to be welded without ferrous layer
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- G—PHYSICS
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- G21C15/24—Promoting flow of the coolant
- G21C15/243—Promoting flow of the coolant for liquids
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- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
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- G—PHYSICS
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- G21C—NUCLEAR REACTORS
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- G21C3/04—Constructional details
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- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
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- G21C3/02—Fuel elements
- G21C3/04—Constructional details
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- G21C3/10—End closures ; Means for tight mounting therefor
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- G—PHYSICS
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- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
- G21C5/126—Carbonic moderators
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K2101/00—Articles made by soldering, welding or cutting
- B23K2101/04—Tubular or hollow articles
- B23K2101/06—Tubes
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- B—PERFORMING OPERATIONS; TRANSPORTING
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- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K2103/00—Materials to be soldered, welded or cut
- B23K2103/50—Inorganic material, e.g. metals, not provided for in B23K2103/02 – B23K2103/26
- B23K2103/52—Ceramics
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- C04B2235/00—Aspects relating to ceramic starting mixtures or sintered ceramic products
- C04B2235/70—Aspects relating to sintered or melt-casted ceramic products
- C04B2235/96—Properties of ceramic products, e.g. mechanical properties such as strength, toughness, wear resistance
- C04B2235/9607—Thermal properties, e.g. thermal expansion coefficient
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- C04B2235/9669—Resistance against chemicals, e.g. against molten glass or molten salts
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- C04B2237/30—Composition of layers of ceramic laminates or of ceramic or metallic articles to be joined by heating, e.g. Si substrates
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- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
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- Y—GENERAL 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
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- Y02E30/00—Energy generation of nuclear origin
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Definitions
- the present invention relates to a nuclear reactor technology, and more particularly to a nuclear fuel rod loaded in a nuclear reactor core and a fuel assembly in which the nuclear fuel rods are bundled.
- fuel assemblies are loaded as reactor fuel in the cores of light water reactors such as boiling water reactors (BWR) and pressurized water reactors (PWR).
- a fuel assembly is one in which a plurality of nuclear fuel rods (also simply referred to as fuel rods) loaded with uranium fuel are aligned and supported by an upper tie plate and a lower tie plate.
- Each reactor fuel rod is loaded with uranium fuel pellets in a fuel cladding tube with a length of about 4 mm and sealed at both ends by end plugs.
- Zirconium alloy (Zircaloy), which has a small thermal neutron absorption cross section and excellent corrosion resistance, has been used as the material for fuel cladding tubes and end plugs. It has excellent neutron economy and is safe in a normal reactor environment. Has been used.
- SiC silicon carbide
- the oxidation rate of SiC in a high-temperature steam environment exceeding 1300 ° C is two orders of magnitude lower than that of zirconium alloys, a significant reduction in hydrogen production can be expected even if a coolant loss accident occurs.
- Patent Document 1 (US 2013/0075039) describes a system for manufacturing a silicon carbide assembly, in which two or more silicon carbide materials and one or more bonded intermediate layers disposed therebetween. And one or more devices for applying energy to the bonding intermediate layer, wherein the bonding intermediate layer is dispersed throughout the first material and the first material that melts at a first temperature.
- a second material that melts at a second temperature lower than the material and the device is operated to soften the first material and melt the second material in applying energy to the joining intermediate layer, And the softening of the first material and the melting of the second material convert the joining intermediate layer into a substantially void-free adhesive material, so that the two or more silicon carbide materials are joined together.
- a silicon carbide assembly manufacturing system is disclosed. . Further, it is disclosed that the bonding intermediate layer contains an aluminum-silicon (Al-Si) alloy.
- Patent Document 2 Japanese Patent Laid-Open No. 2012-2337344 discloses a fuel in which fuel pellets are inserted into the inner surface and an end plug is joined to the end of a fuel cladding tube whose outer surface is in contact with reactor water to seal the fuel pellets.
- a cladding tube assembly wherein the fuel cladding tube and the end plug are both formed of a silicon carbide fiber reinforced composite material reinforced with silicon carbide long fibers, and the fuel cladding tube and the end plug are bonded to each other.
- a fuel cladding tube assembly in which at least a portion in contact with the reactor water is directly joined without interposing a dissimilar material.
- a fuel cladding tube assembly characterized in that it is bonded via a mixture of the above or silicon carbide containing aluminum and yttrium) is disclosed.
- the fuel rod In the first place, the fuel rod is intended to contain radioactive materials (fuel pellets and fission products) so that they do not leak to the outside, and ensuring the airtightness of the joint between the fuel cladding tube and the end plug is an essential requirement. It is.
- liquid phase bonding methods eg, brazing
- the technique described in Patent Document 1 utilizes a liquid phase bonding method and is expected to have appropriate airtightness.
- the fuel rod is required to have heat resistance that can withstand at least 1200 ° C. including the joint.
- One of the high melting point bonding materials is a metal-silicon alloy (metal silicide), and the technique of Patent Document 1 utilizes metal silicide.
- metal silicide metal-silicon alloy
- Patent Document 1 since the Al—Si alloy used in Patent Document 1 is easily dissolved or corroded in the reactor water (eg, 280 to 330 ° C. reactor water) under the normal operating environment of the reactor, When the material comes into contact with the reactor water, another problem arises that the durability of the joint is greatly reduced.
- the object of the present invention is to solve the above-mentioned problems, use SiC material as the material of the fuel cladding tube and the end plug, and combine air tightness, heat resistance and corrosion resistance at the joint portion between the fuel cladding tube and the end plug. It is an object of the present invention to provide a nuclear fuel rod and a fuel assembly in which the fuel rod is bundled.
- One aspect of the present invention is a nuclear fuel rod for a light water reactor, which has a fuel cladding tube and an end plug both made of a silicon carbide material, and a joint portion between the fuel cladding tube and the end plug is
- the fuel cladding tube is formed by brazing and / or diffusion bonding through a predetermined metal bonding material having a solidus temperature of 1200 ° C.
- a reactor fuel rod characterized by being less than / K is provided.
- the present invention can add the following improvements and changes to the reactor fuel rod (I) according to the above-described invention.
- the predetermined metal bonding material is a kind selected from silicon (Si), Si alloy, titanium (Ti), Ti alloy, zirconium (Zr), and Zr alloy, and the predetermined coating metal is Ti , Ti alloy, Zr, and Zr alloy.
- the thickness of the joint coating is 0.1 mm or more and 1 mm or less.
- the silicon carbide material is a silicon carbide fiber-reinforced silicon carbide composite material in which silicon carbide is used as a matrix and silicon carbide fibers are combined.
- the silicon carbide material is a material in which a silicon carbide layer is further formed on part of the surface of the silicon carbide fiber-reinforced silicon carbide composite material.
- the abutting surface of the fuel cladding tube and the end plug at the joint is formed such that the surface direction has an inclination angle of 5 ° to 60 ° with respect to the axial direction of the fuel cladding tube. Yes.
- the fuel cladding tube and the end plug are further fastened by a screw structure.
- Another aspect of the present invention is a fuel assembly configured by bundling a plurality of reactor fuel rods, wherein the reactor fuel rod is the reactor fuel rod according to the present invention described above.
- a fuel assembly characterized by the above is provided.
- a nuclear reactor fuel rod that uses an SiC material as a material for the fuel cladding tube and the end plug, and has airtightness, heat resistance, and corrosion resistance at the joint between the fuel cladding tube and the end plug, and A bundled fuel assembly can be provided.
- FIG. 2 is a schematic view showing an example of a fuel assembly according to the present invention, (a) a longitudinal sectional view, and (b) a transverse sectional view taken along line AA.
- FIG. 1 is a schematic partial sectional view showing an example of a nuclear fuel rod according to the present invention.
- a nuclear fuel rod 10 of the present invention includes a fuel cladding tube 11 and end plugs 12 (12a, 12b) that are joined to both ends of the fuel cladding tube 11 and seal the fuel cladding tube 11.
- a plurality of fuel pellets 13 are loaded in the fuel cladding tube 11.
- one end of the fuel pellets 13 that are connected is pressed by a plenum spring 15. Further, the periphery of the joint between the fuel cladding tube 11 and the end plug 12 is covered with a joint covering 14.
- FIG. 2A is an enlarged schematic cross-sectional view showing an example of a joint portion between a fuel cladding tube and an end plug.
- the joint portion between the fuel cladding tube 11 and the end plug 12a is shown as a representative joint portion, but the joint portion between the fuel cladding tube 11 and the end plug 12b also has the same structure. .
- the illustration of the fuel pellet 13 is omitted.
- the fuel cladding tube 11 and the end plug 12 use a silicon carbide (SiC) material, and in particular, a silicon carbide fiber reinforced silicon carbide composite material (hereinafter referred to as SiC / SiC) in which silicon carbide is used as a matrix and silicon carbide fibers are combined. It is preferable to use (which may be referred to as a composite material). Further, it is preferable to use a material in which a SiC layer is further formed on a part of the surface of the SiC / SiC composite material (for example, a region corresponding to the joint surface of both).
- the method for forming the SiC layer is not particularly limited, and for example, a chemical vapor deposition method (CVD method) or a coating / sintering method can be used.
- the dimensions of the fuel cladding tube 11 are preferably the same as those of a conventional fuel cladding tube made of a zirconium alloy.
- the length is approximately 4 mm
- the outer diameter is approximately 11 mm
- the wall thickness is approximately 1 mm.
- the end plug 12 (12a, 12b) has an insertion straight body portion 12c to be inserted into the fuel cladding tube 11 and an abutting surface 12d that abuts against the end surface of the fuel cladding tube 11, and is joined to the fuel cladding tube 11. It is sometimes preferable that the shape and dimensions are such that no step is generated on the outer surface near the joint.
- the outer diameter of the insertion straight body 12c is formed to be smaller than the inner diameter of the fuel cladding tube 11 by an appropriate amount of play (for example, about 0.02 to 0.5 mm). Preferably it is.
- the fuel cladding tube 11 and the end plug 12a are joined so as to ensure airtightness by brazing and / or diffusion joining via the metal joining material 20.
- the metal bonding material 20 include Si (melting point: 1414 ° C.), Ti (melting point: 1812 ° C.), Zr (melting point: 1855 ° C.), and Si alloy, Ti alloy, and Zr alloy having a solidus temperature of 1200 ° C. or higher.
- One kind selected from can be preferably used.
- the joining of the fuel cladding tube 11 and the end plug 12 is performed, for example, as follows.
- the surface of the fuel cladding tube 11 to be joined and the surface of the end plug 12 (for example, the end surface of the fuel cladding tube 11, the inner surface of the end portion, the insertion straight body portion 12c of the end plug 12 are abutted against each other)
- a film of the metal bonding material 20 is formed on the surface 12d).
- the thickness of the coating is preferably such that it fills the aforementioned play (gap between the inner diameter of the fuel cladding tube 11 and the outer diameter of the insertion straight body 12c) (for example, about 0.01 to 0.25 mm).
- the end plug 12 can be prevented from rattling or falling off.
- conventional methods for example, vapor deposition, thermal spraying, cold spraying, melting
- the fuel cladding tube 11 and the end plug 12 are heated and bonded while being pressed.
- one end of the fuel cladding tube 11 is joined to one end plug (12a or 12b) without loading the fuel pellet 13, and the other end is connected to the other end after the fuel pellet 13 is loaded.
- the entire fuel cladding tube 11 including the joint with the end plug 12 can be heated.
- the joint is locally heated so that the fuel pellets 13 are not heated.
- a conventional method for example, whole heating using a long heating furnace, local heating using a laser, a high frequency, or a local heater
- Ti, Ti alloy, Zr, or Zr alloy is used as the metal bonding material 20
- Ti carbide or Zr carbide is generated by depriving part of the C component from the SiC of the fuel cladding 11 and end plug 12 at the bonding interface.
- a region having a lower C ratio (as a result, a higher Si ratio) than the stoichiometric composition of SiC may occur in the vicinity of the bonding interface.
- Si or Si alloy is used as the metal bonding material 20
- a region having a higher Si ratio than SiC having a stoichiometric composition is naturally generated in the vicinity of the bonding interface.
- Stoichiometric SiC has very high oxidation resistance, but Si alone is an easily oxidizable material. Therefore, if there is an excessive Si component in the joint region, there is a concern that the excessive Si component may be oxidized and corroded (oxidized / dissolved) in the normal operating environment of the light water reactor (for example, reactor water at 280 to 330 ° C.). In other words, if the joint between the fuel cladding tube 11 and the end plug 12 is brought into direct contact with the reactor water, the durability of the joint (that is, the long-term reliability of the fuel rod 10) may be reduced.
- the light water reactor for example, reactor water at 280 to 330 ° C.
- a joint coating 14 made of a coating metal having high corrosion resistance against high-temperature water.
- high-purity water temperature 288 ° C
- PWR pressurized water reactors
- the coating metal one selected from Ti, Ti alloy, Zr, and Zr alloy having high corrosion resistance in the normal operating environment of the light water reactor can be preferably used.
- the thickness of the joint coating 14 is preferably 0.1 mm to 1 mm, and more preferably 0.2 mm to 0.5 mm. When the thickness of the joint coating 14 is less than 0.1 mm, the effect as a corrosion-resistant coating is insufficient. On the other hand, when the thickness of the bonding portion coating 14 exceeds 1 mm, the outer diameter of the portion becomes too thick, which increases the possibility of adversely affecting the flow of cooling water.
- the joint coating 14 can be formed with high adhesion to the base material (the outer surface of the joint and a part of the outer surface of the fuel cladding tube 11 and the end plug 12 adjacent to the joint outer surface)
- the method for forming the partial coating 14 and conventional methods (for example, vapor deposition, thermal spraying, cold spraying) can be used.
- the metal bonding material 20 and the bonding portion coating 14 used in the present invention preferably have an average linear expansion coefficient of less than 10 ppm / K. Temperature fluctuation (thermal expansion) of the fuel rod 10 by using a material with a small difference from the average linear expansion coefficient (4.3 to 6.6 ppm / K) of the SiC material to be joined as the metal joining material 20 and the joint coating 14 -Thermal stress accompanying thermal contraction) can be minimized, and damage to the joint and joint cover 14 can be prevented. On the other hand, when the metal bonding material 20 or the bonding portion coating 14 having an average linear expansion coefficient of 10 ppm / K or more is used, the effect cannot be obtained, and the long-term reliability of the fuel rod 10 as a whole is impaired.
- FIG. 2B is an enlarged schematic cross-sectional view showing another example of the joint between the fuel cladding tube and the end plug
- FIG. 2C is an enlarged cross-sectional view showing still another example of the joint between the fuel cladding tube and the end plug.
- It is a schematic diagram.
- the end surface of the fuel cladding tube 11 and the butting surface 12d of the end plug 12a are in the direction of the fuel cladding. It is not limited to the case of being parallel to the axial direction of the tube 11 (see FIG. 2A), and may have an inclination with respect to the axial direction of the fuel cladding tube 11.
- the inclination angle is preferably 5 ° or more and 60 ° or less with respect to the axial direction of the fuel cladding tube 11.
- An inclination angle of less than 5 ° provides an effect of improving the alignment accuracy, but the effect of increasing the bonding area is sparse.
- the inclination angle exceeds 60 °, chipping is likely to occur at the tip portion of the abutting surface.
- FIG. 2D is an enlarged schematic cross-sectional view showing still another example of the joint portion between the fuel cladding tube and the end plug.
- the embodiment shown in FIG. 2D has a screw structure 12e on the inner surface of the fuel cladding tube 11 and the outer surface of the insertion straight body portion 12c of the end plug 12a.
- the screw structure 12e is desirably a loose screw structure (for example, a shallow valley and a wide screw pitch). Even if it is a loose screw structure, it has a sufficient effect as long as it does not fall out.
- FIG. 3 is a schematic view showing an example of a fuel assembly according to the present invention, (a) a longitudinal sectional view and (b) a transverse sectional view taken along the line AA.
- a fuel assembly 30 shown in FIGS. 3A and 3B is an example of a fuel assembly for a boiling water reactor (BWR), and includes an upper tie plate 31, a lower tie plate 32, and Attached to the upper tie plate 31 and a plurality of fuel rods 10 and water rods 33 held at both ends by the upper and lower tie plates 31 and 32, a fuel support lattice (spacer) 34 for bundling the fuel rods 10 and the water rods 33 And a channel box 35 surrounding the bundle of fuel rods.
- BWR boiling water reactor
- the fuel rods 10 also referred to as full length fuel rods
- the partial length fuel rods 36 and the water rods 33 are bundled and accommodated in a square lattice shape in a channel box 35 having a rectangular cross section. (See FIG. 3B).
- the partial-length fuel rod 36 is a kind of nuclear reactor fuel rod, and is a fuel rod whose effective internal length is shorter than the fuel rod 10 (full length fuel rod) and whose height does not reach the upper tie plate 31. . Further, a handle 37 is fastened to the upper tie plate 31, and when the handle 37 is lifted, the entire fuel assembly 30 can be pulled up.
- the water rod 33 may be the same as the prior art (water rod made of zirconium alloy). However, assuming a coolant loss accident, the water rod 33 is also the present invention.
- the same structure as the fuel rod 10 of the above (having a hollow tube made of SiC material and an end plug, the hollow tube and the end plug are bonded via a metal bonding material 20, and the periphery of the bonded portion is a bonded portion It is preferred to have a coating 14).
- FIG. 4 is a schematic cross-sectional view showing an example of a boiling water reactor cell.
- the BWR cell 40 in the BWR cell 40, four fuel assemblies 30 are arranged in a square shape, and a control rod 41 having a cross-shaped cross section is arranged in the center thereof.
- the cell 40 uses the nuclear reactor fuel rod 10 and the fuel assembly 30 according to the present invention to maintain the same long-term reliability as in the conventional operation environment, and at the time of an accident (for example, loss of coolant). Safety in an accident) can be improved.
- FIG. 5 is a schematic perspective view showing another example of the fuel assembly according to the present invention.
- a fuel assembly 50 shown in FIG. 5 is an example of a fuel assembly for a pressurized water reactor (PWR), and includes a plurality of fuel rods 10, a plurality of control rod guide thimbles 51, and a guide thimble for in-core instrumentation. 52, a plurality of support grids (spacers) 53 that bundle and support them, an upper nozzle 54, and a lower nozzle 55 are provided.
- the upper nozzle 54 and the lower nozzle 55 are components of the skeleton of the fuel assembly 50, and at the same time play a role in positioning the fuel assembly 50 in the core and securing a cooling water flow path.
- FIG. 6 is a schematic cross-sectional view showing an example of a cell of a pressurized water reactor.
- the PWR cell 60 since the control rods are arranged in the fuel assembly 50, the four fuel assemblies 50 are arranged in a square shape as they are.
- the cell 60 also uses the reactor fuel rod 10 and the fuel assembly 50 according to the present invention to maintain the same long-term reliability as in the conventional operation environment, and in the event of an accident (for example, loss of coolant). Safety in an accident) can be improved.
- SiC material bonding experiment using metal bonding material SiC material bonding experiment using metal bonding material
- Examples 1 to 4 and Comparative Example 3 Si, Si alloy and Comparative Examples 1 and 2 (Ni alloy) have a microstructure mainly composed of brazing (brazing).
- Examples 5 to 10 Ti, Ti alloy, Zr, Zr alloy
- a fine structure mainly composed of diffusion bonding diffusion bonding structure
- Comparative Examples 1 and 2 Ni alloy
- cracks in the direction perpendicular to the bonding interface were observed in the metal bonding material. This is due to the large average linear expansion coefficient of Comparative Examples 1 and 2 (Ni alloy) (strictly due to the large difference in the average linear expansion coefficient between SiC and Comparative Examples 1 and 2). This is probably because a large tensile stress was applied to the metal joint during cooling after joining.
- Examples 1 to 10 and Comparative Example 3 no cracks or communicating pores were observed in the joint region.
- Example 3 since the additive elements (Mo, W, Fe) in the Si alloy do not form a chemically stable carbide than SiC, the C component is not deprived from the SiC material at the time of heat bonding. In addition, it is expected to contribute to improving the mechanical strength of the bonding layer.
- the additive elements (Ti, Zr, Ta, Nb, V, Y, Cr) in the Si alloy can form carbides that are chemically more stable than SiC, but the content of each additive element is appropriately set. By controlling this, it is expected that an appropriate reaction layer is formed at the bonding interface and contributes to improvement in bonding strength.
- Comparative Example 3 no problem in microstructural observation was observed, but since the solidus temperature is as low as 577 ° C., it is considered that a problem arises from the viewpoint of heat resistance.
- a joint portion coating (thickness of about 0.2 mm) was formed on the surface of the SiC / SiC composite material plate by vapor deposition or thermal spraying.
- a high temperature water corrosion experiment simulating the normal operating environment of BWR was conducted.
- a mass change was measured after immersing in high temperature water having a temperature of 288 ° C., a dissolved oxygen concentration of 8 ppm and an electric conductivity of less than 0.1 ⁇ S / cm for 500 hours. The results are shown in FIG.
- FIG. 7 is a graph showing the results of high-temperature water corrosion experiments in Comparative Examples 4 to 6 and Examples 11 and 15 to 18.
- an increase in mass means oxidation or hydroxylation of the coated metal by high temperature water, and a decrease in mass means dissolution in high temperature water.
- Comparative Example 4 Al
- Comparative Example 5 Si
- a large weight increase due to the formation of aluminum hydroxide oxide (AlO (OH)) was observed.
- Comparative Example 5 Si
- SiO 2 silicon oxide
- Comparative Example 6 Ni alloy
- Examples 11 and 15 to 18 Zr alloy, Ti alloy, Ti
- ⁇ 1.0 mg / cm 2 or less under the normal operating environment of the reactor, and these materials sufficiently satisfy the requirements. there were.
- the joint coating in the present invention is formed on the SiC material and the joint between the SiC materials, and it is necessary to reduce the difference in linear expansion coefficient from the SiC material as described above.
- Comparative Example 6 Ni alloy
- Comparative Example 6 Ni alloy
- Comparative Example 6 Ni alloy
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Abstract
Description
(i)前記所定の金属接合材は、ケイ素(Si)、Si合金、チタン(Ti)、Ti合金、ジルコニウム(Zr)、およびZr合金から選ばれる一種であり、前記所定の被覆金属は、Ti、Ti合金、Zr、およびZr合金から選ばれる一種である。
(ii)前記接合部被覆の厚さが0.1 mm以上1 mm以下である。
(iii)前記炭化ケイ素材料は、炭化ケイ素をマトリックスとし炭化ケイ素繊維を複合する炭化ケイ素繊維強化炭化ケイ素複合材料である。
(iv)前記炭化ケイ素材料は、前記炭化ケイ素繊維強化炭化ケイ素複合材料の表面の一部に炭化ケイ素層が更に形成されている材料である。
(v)前記接合部における前記燃料被覆管と前記端栓との突き合わせ面は、その面方向が該燃料被覆管の軸方向に対して5°以上60°以下の傾角を有するように形成されている。
(vi)前記燃料被覆管と前記端栓とが、更にねじ構造によって締結されている。
図1は、本発明に係る原子炉燃料棒の一例を示す部分断面模式図である。図1に示したように、本発明の原子炉燃料棒10は、燃料被覆管11と、該燃料被覆管11の両端に接合され燃料被覆管11を封じる端栓12(12a,12b)とを有し、燃料被覆管11内に複数の燃料ペレット13が装填されている。燃料ペレット13を固定するため、連装された燃料ペレット13の一方の端部は、プレナムスプリング15によって押圧されている。また、燃料被覆管11と端栓12との接合部周りは、接合部被覆14で覆われている。
図3は、本発明に係る燃料集合体の一例を示す模式図であり、(a)縦断面図、(b)A-A線の横断面図である。図3(a),(b)に示した燃料集合体30は、沸騰水型原子炉(BWR)用の燃料集合体の一例であり、上部タイプレート31と、下部タイプレート32と、これらの上部・下部タイプレート31,32に両端が保持されている複数の燃料棒10およびウォータロッド33と、燃料棒10およびウォータロッド33を束ねる燃料支持格子(スペーサ)34と、上部タイプレート31に取り付けられ燃料棒束を取り囲むチャンネルボックス35とを備えている。端的に言うと、横断面角筒状のチャンネルボックス35内に、燃料棒10(全長燃料棒とも言う)と部分長燃料棒36とウォータロッド33とが正方格子状に束ねられて収容されている(図3(b)参照)。
複数種の金属接合材を用意し、SiC板同士の接合実験を行った。SiC板は、その表面にSiC層を形成したものを用いた。表1に用意した金属接合材の諸元を示す。
複数種の被覆金属を用意し、SiC/SiC複合材料板上に接合部被覆を形成した後、高温水腐食実験を行った。表2に用意した被覆金属の諸元を示す。
Claims (8)
- 軽水炉用の原子炉燃料棒であって、
共に炭化ケイ素材料からなる燃料被覆管および端栓を有し、
前記燃料被覆管と前記端栓との接合部は、固相線温度が1200℃以上である所定の金属接合材を介したろう付けおよび/または拡散接合によって形成されており、
前記接合部の外表面と該接合部外表面に隣接する前記燃料被覆管および前記端栓の外表面の一部とが、所定の被覆金属からなる接合部被覆で覆われており、
前記所定の金属接合材および前記所定の被覆金属は、その平均線膨張係数が10 ppm/K未満であることを特徴とする原子炉燃料棒。 - 請求項1に記載の原子炉燃料棒において、
前記所定の金属接合材は、ケイ素、ケイ素合金、チタン、チタン合金、ジルコニウム、およびジルコニウム合金から選ばれる一種であり、
前記所定の被覆金属は、チタン、チタン合金、ジルコニウム、およびジルコニウム合金から選ばれる一種であることを特徴とする原子炉燃料棒。 - 請求項1又は請求項2に記載の原子炉燃料棒において、
前記接合部被覆の厚さが0.1 mm以上1 mm以下であることを特徴とする原子炉燃料棒。 - 請求項1乃至請求項3のいずれかに記載の原子炉燃料棒において、
前記炭化ケイ素材料は、炭化ケイ素をマトリックスとし炭化ケイ素繊維を複合する炭化ケイ素繊維強化炭化ケイ素複合材料であることを特徴とする原子炉燃料棒。 - 請求項4に記載の原子炉燃料棒において、
前記炭化ケイ素材料は、前記炭化ケイ素繊維強化炭化ケイ素複合材料の表面の一部に炭化ケイ素層が更に形成されている材料であることを特徴とする原子炉燃料棒。 - 請求項1乃至請求項5のいずれかに記載の原子炉燃料棒において、
前記接合部における前記燃料被覆管と前記端栓との突き合わせ面は、その面方向が該燃料被覆管の軸方向に対して5°以上60°以下の傾角を有するように形成されていることを特徴とする原子炉燃料棒。 - 請求項1乃至請求項6のいずれかに記載の原子炉燃料棒において、
前記燃料被覆管と前記端栓とが、更にねじ構造によって締結されていることを特徴とする原子炉燃料棒。 - 複数の原子炉燃料棒を束ねて構成される燃料集合体であって、
前記原子炉燃料棒が、請求項1乃至請求項7のいずれかに記載の原子炉燃料棒であることを特徴とする燃料集合体。
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JP2016561127A JP6300953B2 (ja) | 2014-11-26 | 2014-11-26 | 原子炉燃料棒およびそれを束ねた燃料集合体 |
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JP2021503427A (ja) * | 2017-10-19 | 2021-02-12 | ゼネラル・アトミックスGeneral Atomics | 加圧されたセラミック構成体の接合および封止 |
JP7353277B2 (ja) | 2017-10-19 | 2023-09-29 | ゼネラル・アトミックス | 加圧されたセラミック構成体の接合および封止 |
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JP7453941B2 (ja) | 2021-07-02 | 2024-03-21 | 日立Geニュークリア・エナジー株式会社 | 原子炉燃料棒、該燃料棒の製造方法および該燃料棒を束ねた燃料集合体 |
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US10796807B2 (en) | 2020-10-06 |
EP3226247A1 (en) | 2017-10-04 |
EP3226247A4 (en) | 2018-06-20 |
EP3226247B1 (en) | 2019-05-29 |
JP6300953B2 (ja) | 2018-03-28 |
US20170330638A1 (en) | 2017-11-16 |
JPWO2016084146A1 (ja) | 2017-08-31 |
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