WO2020093246A1 - Tube for nuclear fuel assembly and fuel cladding - Google Patents
Tube for nuclear fuel assembly and fuel cladding Download PDFInfo
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- WO2020093246A1 WO2020093246A1 PCT/CN2018/114204 CN2018114204W WO2020093246A1 WO 2020093246 A1 WO2020093246 A1 WO 2020093246A1 CN 2018114204 W CN2018114204 W CN 2018114204W WO 2020093246 A1 WO2020093246 A1 WO 2020093246A1
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- Prior art keywords
- sic
- layer
- tube
- nuclear fuel
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B32—LAYERED PRODUCTS
- B32B—LAYERED PRODUCTS, i.e. PRODUCTS BUILT-UP OF STRATA OF FLAT OR NON-FLAT, e.g. CELLULAR OR HONEYCOMB, FORM
- B32B15/00—Layered products comprising a layer of metal
- B32B15/14—Layered products comprising a layer of metal next to a fibrous or filamentary layer
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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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
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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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the invention relates to the technical field of nuclear fuel, in particular to a nuclear fuel assembly tube and a fuel cladding.
- Improvements, upgrades, and even full replacements were made to reduce the enthalpy of heat and hydrogen generation of the cladding and high-temperature water vapor, improve the structural integrity and functionality of the cladding at 1200 ° C accident high temperature, and enhance the cladding's bondage to fission gas Ability etc.
- the existing nuclear fuel uses the SiC composite cladding as an important candidate cladding for accident-tolerant fuel (ATF) in the post-Fukushima era.
- ATF accident-tolerant fuel
- the existing SiC composite cladding has the following deficiencies:
- SiC and its composite materials are inorganic non-metallic ceramic materials. Even if they are whiskers and fiber reinforced and toughened, they are still brittle materials. In the service environment of the reactor, there are external pressure of coolant, internal pressure of cladding, thermal stress and radiation Due to multiple thermomechanical effects such as damage, the generation and propagation of microcracks is inevitable, which will lead to the leakage of fission products;
- SiC and its composite materials have high hardness and high rigidity.
- PCMI interaction force
- SiC and its composite materials are used as the cladding, and the outside is corroded by the coolant. Under normal working conditions, SiC and the high-temperature and high-pressure primary water react to form SiO 2 and dissolve in water to form silicic acid, and the corrosion increases with time;
- SiC and its composite materials are used as cladding.
- the swelling of the core causes the interface chemical reaction (PCCI) after the core contacts the cladding.
- PCCI interface chemical reaction
- the UO 2 core reacts with the SiC cladding. accelerate.
- the technical problem to be solved by the present invention is to provide an improved nuclear fuel assembly tube and fuel cladding.
- the technical solution adopted by the present invention to solve its technical problems is to provide a tube of nuclear fuel assembly, including a SiC fiber toughened SiC composite layer, a dense structural layer provided on the inner periphery of the SiC fiber toughened SiC composite layer, and an arrangement An environmental shielding layer on the periphery of the SiC fiber toughened SiC composite layer; the dense structure layer is a metal inner layer.
- the inner metal layer is made of at least one element and / or alloy of niobium, zirconium, yttrium, tantalum, vanadium, titanium, chromium, iron, cobalt, and nickel.
- the thickness of the inner metal layer is 0.1mm-0.5mm; the thickness of the SiC fiber toughened SiC composite layer is 0.3mm-1mm;
- the outer diameter of the pipe is 9.0mm-14mm.
- the environment shielding layer is a densified corrosion-resistant layer; the densified corrosion-resistant layer includes a ceramic coating and / or a metal coating.
- the ceramic coating includes at least one of SiC ceramic coating, CrN ceramic coating, Al 2 O 3 ceramic coating and MAX phase ceramic coating; wherein the MAX phase includes Cr 2 AlC and Cr 3 AlC 2 , Cr 2 SiC, Cr 3 SiC 2 , Ti 3 SiC 2 , Ti 2 SiC, Ti 3 AlC 2 , one or more of Ti 2 AlC, Zr 2 AlC, Zr 2 SiC;
- the metal coating includes one or more of Cr, FeCrAl, FeCrSi, CrNi, CrAl, and Ni.
- the environmental shielding layer is a metal layer or a ceramic layer.
- the metal layer is made of one or more of Cr, FeCrAl, FeCrSi, CrNi, CrAl, Ni;
- the ceramic layer is made of one or more of SiC, CrN, Al 2 O 3 , and MAX phase; wherein the MAX phase includes Cr 2 AlC, Cr 3 AlC 2 , Cr 2 SiC, Cr 3 SiC 2 , Ti 3 One or more of SiC 2 , Ti 2 SiC, Ti 3 AlC 2 , Ti 2 AlC, Zr 2 AlC, Zr 2 SiC.
- the thickness of the inner metal layer is 0.1mm-0.3mm; the thickness of the SiC fiber toughened SiC composite layer is 0.3mm-1mm; the thickness of the environmental shielding layer is 0.02mm-0.2mm;
- the outer diameter of the pipe is 9.0mm-14mm.
- the SiC fiber-reinforced SiC composite layer is made of a SiC fiber braided, wound or fiber cloth coiled tube, a chemical vapor deposition process is used to prepare an interface layer on the surface of the SiC fiber, a precursor impregnation cracking process, a chemical vapor impregnation process, The melt infiltration process or nano-dipping and transient eutectic phase process make it dense.
- the tube material of the nuclear fuel assembly is a fuel cladding, a guide tube or a heat exchange tube.
- the invention also provides a fuel cladding, which includes a SiC fiber toughened SiC composite layer, a dense structure layer provided on the inner periphery of the SiC fiber toughened SiC composite layer, and a periphery of the SiC fiber toughened SiC composite layer Environmental shielding layer; the dense structural layer is a metal inner layer;
- the inner metal layer is made of at least one element and / or alloy of niobium, zirconium, yttrium, tantalum, vanadium, titanium, chromium, iron, cobalt, and nickel.
- the tube is formed by the metal inner layer combined with the SiC fiber toughened SiC composite layer, which is suitable for the fuel cladding, guide tube and other nuclear fuel component tubes.
- the SiC fiber toughened SiC composite layer plays a role of strength support and steam oxidation resistance under accident conditions above 1200 °C;
- the metal inner layer solves the airtightness of the cladding and other pipes Problems, to avoid the leakage of fission gas due to SiC micro-cracks, alleviate the interaction force (PCMI) and chemical reaction (PCCI) between the cladding and the core block, and avoid the damage of the cladding;
- the cladding and other pipes are improved through the environmental shielding layer The resistance to water and heat corrosion, to avoid the phenomenon of dissolved silicon.
- the invention is suitable for the application of fault-tolerant nuclear fuel cladding and components, and greatly improves the anti-accident capability and safety threshold of nuclear reactors to maintain the structure and functional integrity of nuclear fuel components under severe accident conditions.
- FIG. 1 is a schematic cross-sectional structure diagram of a pipe material according to a first embodiment of the present invention
- FIG. 2 is a schematic cross-sectional structure diagram of a pipe material according to a second embodiment of the present invention.
- the nuclear fuel assembly tube 10 of the first embodiment of the present invention includes a SiC fiber toughened SiC composite layer 11 and a metal inner layer 12 provided on the inner periphery of the SiC fiber toughened SiC composite layer 11 to The environmental shielding layer 13 on the periphery of the SiC composite layer 11 toughened by SiC fibers.
- the SiC fiber toughened SiC composite layer (SiC f / SiC layer) 11 is the main body of the pipe 10, which plays a role of strength support and steam oxidation resistance under accident conditions above 1200 ° C; the metal inner layer 12 is in The inner side of the SiC fiber toughened SiC composite layer 11 forms a metal inner tube.
- the tube 10 may be a fuel cladding, a guide tube, a heat exchange tube, or the like in a nuclear fuel assembly.
- the metal inner layer 12 plays the role of realizing the impermeability of the cladding, avoiding the leakage of fission gas due to SiC micro-cracks or pores; on the other hand, it alleviates the core-cladding interaction Through the inner metal layer 12, the interaction force (PCMI) and chemical reaction (PCCI) between the SiC cladding and the core block are alleviated to avoid the cladding damage.
- PCMI interaction force
- PCCI chemical reaction
- the inner metal layer 12 is a dense structure layer, and the selected material has the following characteristics: it has a high melting point matched with SiC, a low neutron absorption cross section, and good chemical compatibility with SiC.
- the inner metal layer 12 may be selected from niobium (Nb), zirconium (Zr), yttrium (Y), tantalum (Ta), vanadium (V), titanium (Ti), chromium (Cr), iron (Fe), cobalt (Co), nickel (Ni) is made of at least one element, alloy, or element and alloy.
- Nb is a refractory metal with a melting point of 2477 ° C, which is more compatible with SiC; in the neutron absorption cross section, Nb (1.15 barn) ⁇ molybdenum Mo (2.6 barn) ⁇ tungsten W (18.3 barn) ⁇ tantalum Ta (20.6 barn) ⁇ hafnium Hf (104 barn)
- the metal inner layer 12 is made of a single element of Nb, Zr, Y or an alloy thereof.
- the environmental shielding layer 13 is a thin layer covering the outer periphery of the SiC fiber-reinforced SiC composite layer 11, which protects it against water, heat, and corrosion, and avoids the phenomenon of silicon dissolution.
- the environmental shielding layer 13 is a densified corrosion-resistant layer; the densified corrosion-resistant layer includes a ceramic coating and / or a metal coating, which may be a ceramic coating or a metal coating, or a combination of both .
- the environmental shielding layer 13 may use melt slurry, laser cladding, physical vapor deposition, sputtering, thermal spraying, plasma spraying, wire arc coating, chemical vapor deposition, electroplating, electrophoretic deposition, electroless coating, and atomic layer deposition, etc. At least one of the methods is formed.
- the ceramic coating includes but is not limited to at least one of SiC ceramic coating, CrN ceramic coating, Al 2 O 3 ceramic coating, and MAX phase ceramic coating; where the MAX phase includes but is not limited to Cr 2 AlC, One or more of Cr 3 AlC 2 , Cr 2 SiC, Cr 3 SiC 2 , Ti 3 SiC 2 , Ti 2 SiC, Ti 3 AlC 2 , Ti 2 AlC, Zr 2 AlC, Zr 2 SiC.
- the metal coating includes but is not limited to one or more of Cr, FeCrAl, FeCrSi, CrNi, CrAl, Ni.
- the ceramic coating is preferably a SiC ceramic coating, a CrN ceramic coating, a Cr 2 AlC ceramic coating, or a Ti 3 SiC 2 ceramic coating.
- the metal coating is preferably a Cr coating or FeCrAl coating.
- the thickness of the inner metal layer 12 may be 0.1 mm-0.5 mm, preferably 0.1 mm-0.3 mm, and the thickness of the SiC fiber-reinforced SiC composite layer 11 is 0.3 mm-1 mm, preferably 0.3 mm-0.6 mm.
- the outer diameter of the tube 10 is 9.0 mm-14 mm, preferably 9.5 mm-11 mm.
- the tube material 20 of the nuclear fuel assembly of the second embodiment of the present invention includes a SiC fiber toughened SiC composite layer 21 and a metal inner layer 22 provided on the inner periphery of the SiC fiber toughened SiC composite layer 21 to The environmental shielding layer 23 on the periphery of the SiC composite layer 21 toughened by SiC fibers.
- the SiC fiber-reinforced SiC composite layer (SiC f / SiC) 21 is the main body of the tube 20, which plays a role in strength support and steam oxidation resistance under accident conditions above 1200 ° C; the metal inner layer 22 is in SiC The inner side of the fiber-reinforced SiC composite layer 21 forms a metal inner tube.
- the tube 20 may be a fuel cladding, a guide tube, a heat exchange tube, or the like in a nuclear fuel assembly.
- the metal inner layer 22 plays the role of realizing the impermeability of the cladding, avoiding the leakage of fission gas due to SiC micro-cracks or pores; Through the inner metal layer 22, the interaction force (PCMI) and chemical reaction (PCCI) between the SiC cladding and the core block are alleviated, and the cladding is prevented from being damaged.
- the environmental shielding layer 23 plays a role of environmental shielding against water, heat, and corrosion, and avoids the phenomenon of dissolved silicon.
- the inner metal layer 22 is a dense structure layer, which can be selected from niobium (Nb), zirconium (Zr), yttrium (Y), tantalum (Ta), vanadium (V), titanium (Ti), chromium (Cr), and iron (Fe ), Cobalt (Co), nickel (Ni) at least one element, alloy, or element and alloy.
- the inner metal layer 12 is made of a single element of Nb, Zr, Y or an alloy thereof.
- the environmental shielding layer 23 is a dense structure layer, which may specifically be a metal layer or a ceramic layer.
- the metal layer is made of one or more of Cr, FeCrAl, FeCrSi, CrNi, CrAl, Ni, preferably Cr or FeCrAl.
- the ceramic layer is made of one or more of SiC, CrN, Al 2 O 3 and MAX phase; where the MAX phase includes Cr 2 AlC, Cr 3 AlC 2 , Cr 2 SiC, Cr 3 SiC 2 and Ti 3 SiC 2 , Ti 2 SiC, Ti 3 AlC 2 , Ti 2 AlC, Zr 2 AlC, Zr 2 SiC one or more; ceramic layer is preferably made of SiC, CrN, Cr 2 AlC or Ti 3 SiC 2 .
- the environmental shielding layer 23 may be melt-hanging slurry, laser cladding, physical vapor deposition, sputtering, thermal spraying, plasma spraying, wire arc coating, chemical vapor deposition, electroplating, electrophoretic deposition, electroless coating, atomic layer deposition, etc. At least one of the methods is formed.
- the thickness of the metal inner layer 22 may be 0.1 mm-0.5 mm, preferably 0.1 mm-0.3 mm; the thickness of the SiC fiber toughened SiC composite layer 21 is 0.3 mm-1 mm, preferably 0.3 mm-0.6 mm; The thickness of the environmental shielding layer 23 is 0.02 mm-0.2 mm, preferably 0.05 mm-0.1 mm.
- the outer diameter of the tube 20 is 9.0mm-14mm, preferably 9.5 mm -11mm.
- the inner metal layer 12 (22) can be made by, but not limited to, rolling, drawing, coiling, heat treatment, annealing, etc.
- the outer surface may undergo pre-oxidation treatment, pre-carbonization treatment, and pre-nitridation treatment.
- the SiC fiber-reinforced SiC composite layer 11 (21) is made of SiC fiber braided, wound or fiber cloth coiled tube.
- the chemical vapor deposition process (CVD) is used to prepare the interface layer on the SiC fiber surface.
- the precursor impregnation cracking process (PIP), The chemical vapor impregnation process (CVI), melt infiltration process (MI) or nano impregnation and transient eutectic phase process (NITE) realize the dense sintering of the SIC matrix to form the SiC fiber toughened SiC composite layer 11 (21).
- the metal inner layer tube with a wall thickness of 0.2 mm and an outer diameter of 8.6 mm is made of metal niobium with good formability and ductility through multiple cold rolling and heat treatments, and the outer surface is carbonized.
- the third-generation SiC fiber with high stoichiometric ratio is braided on the metal niobium tube to form a SiC composite skeleton with a thickness of 0.5mm.
- the chemical vapor deposition method is used to prepare the pyrolytic carbon PyC interface layer on the surface of the SiC fiber, and then the precursor is impregnated and cracked.
- PIP Polycarbosilane
- a plasma spraying process is used to prepare a metal Cr layer with a thickness of 0.1 mm on the surface of the SiC f / SiC composite material layer, thereby producing a cermet-type SiC composite cladding tube.
- the high-temperature tensile strength of the cermet-type SiC composite cladding tube at 1200 ° C is 200 MPa, which is more than 10 times that of the zirconium alloy.
- the cladding tube is oxidized at 1200 ° C for 1 hour after steam oxidation.
- the oxidative weight gain of the shell is only 0.2 mg / cm 2
- the oxidized weight gain of the uncoated zirconium alloy cladding under the same conditions is 37 mg / cm 2 , indicating that the cladding effectively reduces the high-temperature steam oxidation of the zirconium alloy nuclear fuel cladding Gain weight by 2 orders of magnitude.
- the metal inner layer tube with a wall thickness of 0.3 mm and an outer diameter of 8.8 mm is made of metal zirconium with good formability and ductility through multiple cold rolling and heat treatments, and its outer surface is pre-oxidized.
- the third-generation SiC fiber with high stoichiometric ratio is woven into a SiC composite skeleton with a thickness of 0.4mm on the metal zirconium tube.
- the chemical vapor deposition method is used to prepare the pyrolytic carbon PyC interface layer on the surface of the SiC fiber, and then the precursor is impregnated and cracked.
- PIP Polycarbosilane
- a metal Cr layer with a thickness of 0.15 mm is prepared on the surface of the SiC f / SiC composite material layer, thereby producing a cermet-type SiC composite cladding tube.
- the high-temperature tensile strength of the cermet-type SiC composite cladding tube at 1200 ° C is 180 MPa; in terms of high-temperature oxidation resistance, the oxidation weight gain of the cladding is only 0.15 mg after steam oxidation at 1200 ° C for 1 hour / cm 2 .
- the metal inner layer tube with a wall thickness of 0.25mm and an outer diameter of 8.7mm is made of metal yttrium with good formability and ductility through multiple cold rolling and heat treatments, and its outer surface is pre-oxidized.
- the third-generation SiC fiber with high stoichiometric ratio is woven into a SiC composite skeleton with a thickness of 0.6 mm on the metal zirconium tube.
- the chemical vapor deposition method is used to prepare the pyrolytic carbon PyC interface layer on the surface of the SiC fiber.
- CVI The trichloromethylsilane is cracked, impregnated and deposited to form a dense and highly crystalline SiC f / SiC composite material layer.
- a magnetron sputtering process was used to prepare a metal FeCrAl layer with a thickness of 0.05 mm on the surface of the SiC f / SiC composite material layer, thereby producing a cermet-type SiC composite cladding tube.
- the high-temperature tensile strength of the cermet-type SiC composite cladding tube at 1200 ° C is 230 MPa; in terms of high-temperature oxidation resistance, the oxidation weight gain of the cladding is only 0.12 mg after oxidizing at 1200 ° C for 1 hour. / cm 2 .
- a metal inner layer tube with a wall thickness of 0.1 mm and an outer diameter of 8.5 mm is made of metal niobium with good formability and ductility through multiple cold rolling and heat treatments, and its outer surface is nitrided.
- the third-generation SiC fiber with high stoichiometric ratio is braided on the metal zirconium tube to form a SiC composite skeleton with a thickness of 0.7mm.
- the chemical vapor deposition method is used to prepare the pyrolytic carbon PyC interface layer on the surface of the SiC fiber, and then the SiC nano powder is used.
- a dense and highly crystallized SiC f / SiC composite layer is formed.
- a magnetron sputtering process was used to prepare a Cr 2 AlC coating with a thickness of 0.02 mm on the surface of the SiC f / SiC composite material layer, thereby producing a cermet-type SiC composite cladding tube.
- the high-temperature tensile strength of the cermet-type SiC composite cladding tube at 1200 ° C is 250 MPa; in terms of high-temperature oxidation resistance, after 1 hour of steam oxidation at 1200 ° C, the oxidized weight gain of the cladding is only 0.5 mg / cm 2 .
- a metal inner layer tube with a wall thickness of 0.1 mm and an outer diameter of 8.5 mm is made of metal tantalum with good formability and ductility through multiple cold rolling and heat treatments, and the outer surface is carbonized.
- the third-generation SiC fiber with high stoichiometric ratio is woven into a SiC composite skeleton with a thickness of 0.7 mm on the metal zirconium tube.
- the chemical vapor deposition method is used to prepare the pyrolytic carbon PyC interface layer on the surface of the SiC fiber, and then the precursor is impregnated and cracked.
- PIP Polycarbosilane
- a chemical vapor deposition (CVD) process was used to prepare a dense SiC coating with a high crystallinity of 0.02 mm on the surface of the SiC f / SiC composite material layer to produce a cermet-type SiC composite cladding tube.
- the high-temperature tensile strength of the cermet-type SiC composite cladding tube at 1200 ° C is 190 MPa; in terms of high-temperature oxidation resistance, after oxidizing at 1200 ° C for 1 hour, the oxidized weight gain of the cladding is only 0.08 mg / cm 2 .
- the pipe material of the present invention is not limited to nuclear fuel assemblies such as nuclear fuel cladding and heat exchange tubes, but is also applicable to fields such as thermal power plants, chemical industry, and medicine.
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Abstract
Description
Claims (11)
- 一种核燃料组件的管材,其特征在于,包括SiC纤维增韧SiC复合层、设置在所述SiC纤维增韧SiC复合层内周的致密结构层、以及设置在所述SiC纤维增韧SiC复合层外周的环境屏蔽层;所述致密结构层为金属内层。A nuclear fuel assembly tube characterized by comprising a SiC fiber toughened SiC composite layer, a dense structure layer provided on the inner periphery of the SiC fiber toughened SiC composite layer, and a SiC fiber toughened SiC composite layer The environmental shielding layer on the outer periphery; the dense structural layer is a metal inner layer.
- 根据权利要求1所述的核燃料组件的管材,其特征在于,所述金属内层选用铌、锆、钇、钽、钒、钛、铬、铁、钴、镍中至少一种单质和/或合金制成。The nuclear fuel assembly tube according to claim 1, wherein the metal inner layer is selected from at least one element and / or alloy of niobium, zirconium, yttrium, tantalum, vanadium, titanium, chromium, iron, cobalt, and nickel production.
- 根据权利要求1所述的核燃料组件的管材,其特征在于,所述金属内层的厚度为0.1mm-0.5mm;所述SiC纤维增韧SiC复合层的厚度为0.3mm-1mm;The nuclear fuel assembly tube according to claim 1, wherein the thickness of the metal inner layer is 0.1mm-0.5mm; the thickness of the SiC fiber toughened SiC composite layer is 0.3mm-1mm;所述管材的外径为9.0mm-14mm。The outer diameter of the pipe is 9.0mm-14mm.
- 根据权利要求1所述的核燃料组件的管材,其特征在于,所述环境屏蔽层为致密化耐腐蚀层;所述致密化耐腐蚀层包括陶瓷涂层和/或金属涂层。The tube material of a nuclear fuel assembly according to claim 1, wherein the environmental shielding layer is a densified corrosion-resistant layer; the densified corrosion-resistant layer includes a ceramic coating and / or a metal coating.
- 根据权利要求4所述的核燃料组件的管材,其特征在于,所述陶瓷涂层包括SiC陶瓷涂层、CrN陶瓷涂层、Al 2O 3陶瓷涂层、MAX相陶瓷涂层中的至少一种;其中MAX相包括Cr 2AlC、Cr 3AlC 2、Cr 2SiC、Cr 3SiC 2、Ti 3SiC 2、Ti 2SiC、Ti 3AlC 2、Ti 2AlC、Zr 2AlC、Zr 2SiC中的一种或多种; The nuclear fuel assembly tube according to claim 4, wherein the ceramic coating comprises at least one of SiC ceramic coating, CrN ceramic coating, Al 2 O 3 ceramic coating, and MAX phase ceramic coating ; Where the MAX phase includes Cr 2 AlC, Cr 3 AlC 2 , Cr 2 SiC, Cr 3 SiC 2 , Ti 3 SiC 2 , Ti 2 SiC, Ti 3 AlC 2 , Ti 2 AlC, Zr 2 AlC, Zr 2 SiC One or more所述金属涂层包括于Cr、FeCrAl、FeCrSi、CrNi、CrAl、Ni中的一种或多种。The metal coating includes one or more of Cr, FeCrAl, FeCrSi, CrNi, CrAl, and Ni.
- 根据权利要求1所述的核燃料组件的管材,其特征在于,所述环境屏蔽层为金属层或陶瓷层。The tube material of a nuclear fuel assembly according to claim 1, wherein the environmental shielding layer is a metal layer or a ceramic layer.
- 根据权利要求6所述的核燃料组件的管材,其特征在于,所述金属层为Cr、FeCrAl、FeCrSi、CrNi、CrAl、Ni中的一种或多种制成;The nuclear fuel assembly tube according to claim 6, wherein the metal layer is made of one or more of Cr, FeCrAl, FeCrSi, CrNi, CrAl, Ni;所述陶瓷层为SiC、CrN、Al 2O 3、MAX相中的一种或多种制成;其中MAX相包括Cr 2AlC、Cr 3AlC 2、Cr 2SiC、Cr 3SiC 2、Ti 3SiC 2、Ti 2SiC、Ti 3AlC 2、Ti 2AlC、Zr 2AlC、Zr 2SiC中的一种或多种。 The ceramic layer is made of one or more of SiC, CrN, Al 2 O 3 , and MAX phase; wherein the MAX phase includes Cr 2 AlC, Cr 3 AlC 2 , Cr 2 SiC, Cr 3 SiC 2 , Ti 3 One or more of SiC 2 , Ti 2 SiC, Ti 3 AlC 2 , Ti 2 AlC, Zr 2 AlC, Zr 2 SiC.
- 根据权利要求6所述的核燃料组件的管材,其特征在于,所述金属内层的厚度为0.1mm-0.3mm;所述SiC纤维增韧SiC复合层的厚度为0.3mm-1mm;所述环境屏蔽层的厚度为0.02mm-0.2mm;The nuclear fuel assembly tube according to claim 6, wherein the thickness of the metal inner layer is 0.1mm-0.3mm; the thickness of the SiC fiber-reinforced SiC composite layer is 0.3mm-1mm; the environment The thickness of the shielding layer is 0.02mm-0.2mm;所述管材的外径为9.0mm-14mm。The outer diameter of the pipe is 9.0mm-14mm.
- 根据权利要求1-8任一项所述的核燃料组件的管材,其特征在于,所述SiC纤维增韧SiC复合层通过SiC纤维编织、缠绕或纤维布的卷管,采用化学气相沉积工艺在SiC纤维表面制备界面层,采用先驱体浸渍裂解工艺、化学气相浸渍工艺、熔融渗透工艺或者纳米浸渍与瞬时共晶相工艺使其致密化。The tube material for nuclear fuel assembly according to any one of claims 1-8, wherein the SiC fiber-reinforced SiC composite layer is a SiC fiber braided, wound, or fiber cloth coiled tube, using a chemical vapor deposition process in SiC The interface layer is prepared on the surface of the fiber, which is densified by a precursor impregnation cracking process, a chemical vapor impregnation process, a melt infiltration process, or a nano impregnation and transient eutectic phase process.
- 根据权利要求1-8任一项所述的核燃料组件的管材,其特征在于,所述核燃料组件的管材为燃料包壳、导向管或热交换管。The nuclear fuel assembly tube according to any one of claims 1-8, wherein the nuclear fuel assembly tube is a fuel cladding, a guide tube, or a heat exchange tube.
- 一种燃料包壳,其特征在于,包括SiC纤维增韧SiC复合层、设置在所述SiC纤维增韧SiC复合层内周的致密结构层、以及设置在所述SiC纤维增韧SiC复合层外周的环境屏蔽层;所述致密结构层为金属内层;A fuel cladding, characterized in that it comprises a SiC fiber toughened SiC composite layer, a dense structure layer provided on the inner periphery of the SiC fiber toughened SiC composite layer, and a periphery of the SiC fiber toughened SiC composite layer Environmental shielding layer; the dense structural layer is a metal inner layer;所述金属内层选用铌、锆、钇、钽、钒、钛、铬、铁、钴、镍中至少一种单质和/或合金制成。The inner metal layer is made of at least one element and / or alloy of niobium, zirconium, yttrium, tantalum, vanadium, titanium, chromium, iron, cobalt, and nickel.
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WO2023070067A1 (en) * | 2021-10-21 | 2023-04-27 | Westinghouse Electric Company Llc | Annular nuclear fuel rod |
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US20170365364A1 (en) * | 2016-06-21 | 2017-12-21 | Westinghouse Electric Company Llc | METHOD OF MANUFACTURING A SiC COMPOSITE FUEL CLADDING WITH INNER Zr ALLOY LINER |
CN108290387A (en) * | 2015-12-02 | 2018-07-17 | 西屋电气有限责任公司 | MULTILAYER COMPOSITE fuel can system with elevated-temperature seal and disaster tolerance |
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