WO2020093246A1 - Tube for nuclear fuel assembly and fuel cladding - Google Patents

Tube for nuclear fuel assembly and fuel cladding Download PDF

Info

Publication number
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
Authority
WO
WIPO (PCT)
Prior art keywords
sic
layer
tube
nuclear fuel
alc
Prior art date
Application number
PCT/CN2018/114204
Other languages
French (fr)
Chinese (zh)
Inventor
刘彤
李锐
薛佳祥
武海龙
李雷
肖玲
许多挺
任啟森
廖业宏
Original Assignee
中广核研究院有限公司
广东核电合营有限公司
中国广核集团有限公司
中国广核电力股份有限公司
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 中广核研究院有限公司, 广东核电合营有限公司, 中国广核集团有限公司, 中国广核电力股份有限公司 filed Critical 中广核研究院有限公司
Priority to PCT/CN2018/114204 priority Critical patent/WO2020093246A1/en
Publication of WO2020093246A1 publication Critical patent/WO2020093246A1/en

Links

Classifications

    • 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
    • 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
    • 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.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Metallurgy (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Laminated Bodies (AREA)

Abstract

A tube for a nuclear fuel assembly and a fuel cladding. The tube for a nuclear fuel assembly 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 an environmental shielding layer provided on the outer periphery of the SiC fiber-toughened SiC composite layer, the dense structure layer being a metal inner layer. The tube is formed by the metal inner layer combined with the SiC fiber-toughened SiC composite layer and is applicable to fuel claddings and tubes for nuclear fuel assemblies such as guide pipes.

Description

核燃料组件的管材及燃料包壳Nuclear fuel assembly tubes and fuel cladding 技术领域Technical field
本发明涉及核燃料技术领域，尤其涉及一种核燃料组件的管材及燃料包壳。The invention relates to the technical field of nuclear fuel, in particular to a nuclear fuel assembly tube and a fuel cladding.
背景技术Background technique
日本福岛核事故发生以后，核电安全再次成为国际民众普遍关注的焦点，而如何进一步提高核电安全性特别是提高核反应堆抵抗超设计基准核事故的安全阈值也成为核能可持续发展的重要议题。事故容错核燃料（Accident Tolerant Fuels，ATF）这一全新核安全技术概念正是在这一背景下诞生的，并逐渐成为世界核电工业最重要的研究课题之一，其目的是对现有锆合金/二氧化铀燃料体系进行改进升级甚至全面更新替换以实现降低包壳与高温水蒸气的反应焓热和氢气生成量、提升包壳在1200℃事故高温下的结构完整性与功能性以及增强包壳对裂变气体的束缚能力等。After the Fukushima nuclear accident in Japan, nuclear power safety has once again become the focus of general concern of the international public, and how to further improve the safety of nuclear power, especially the safety threshold of nuclear reactors against nuclear accidents beyond the design basis has also become an important issue for the sustainable development of nuclear energy. Accident fault-tolerant nuclear fuel (Accident Tolerant Fuels (ATF), a new nuclear safety technology concept was born under this background, and gradually became one of the world ’s most important research topics in the nuclear power industry. Its purpose is to treat the existing zirconium alloy / uranium dioxide fuel system. 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.
基于上述的目的，现有的核燃料中使用了SiC复合材料包壳作为后福岛时代的事故容错燃料（ATF）重要候选包壳。然而，现有的SiC复合材料包壳存在以下不足：Based on the above purpose, the existing nuclear fuel uses the SiC composite cladding as an important candidate cladding for accident-tolerant fuel (ATF) in the post-Fukushima era. However, the existing SiC composite cladding has the following deficiencies:
1、SiC及其复合材料属于无机非金属陶瓷材料，即便是晶须、纤维增强增韧，仍然属于脆性材料，在反应堆服役环境下，存在冷却剂外压、包壳内压、热应力、辐照损伤等多重热机械作用，微裂纹的产生和扩展不可避免，会导致裂变产物的泄露；1. 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;
2、SiC及其复合材料硬度高、刚性大，作为核燃料包壳，在高燃耗时，芯块肿胀导致芯块与包壳接触后发生相互作用力（PCMI），易导致SiC包壳产生裂纹，造成包壳破损和核泄漏；2. SiC and its composite materials have high hardness and high rigidity. As a nuclear fuel cladding, at high fuel consumption, the swelling of the core causes the interaction force (PCMI) between the core and the cladding, which may cause cracks in the SiC cladding , Causing damage to the cladding and nuclear leakage;
3、SiC及其复合材料作为包壳，外侧有冷却剂的腐蚀，SiC与高温高压一回路水在正常工况下，反应生成SiO 2后溶水形成硅酸，腐蚀随时间加剧； 3. 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;
4、SiC及其复合材料作为包壳，在高燃耗时，芯块肿胀导致芯块与包壳接触后发生界面化学反应（PCCI），在1300℃以上，UO 2芯块与SiC包壳反应加速。 4. SiC and its composite materials are used as cladding. At high burnup, the swelling of the core causes the interface chemical reaction (PCCI) after the core contacts the cladding. Above 1300 ℃, the UO 2 core reacts with the SiC cladding. accelerate.
技术问题technical problem
本发明要解决的技术问题在于，提供一种改进的核燃料组件的管材及燃料包壳。The technical problem to be solved by the present invention is to provide an improved nuclear fuel assembly tube and fuel cladding.
技术解决方案Technical solution
本发明解决其技术问题所采用的技术方案是：提供一种核燃料组件的管材，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。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.
优选地，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。Preferably, 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.
优选地，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；Preferably, 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;
所述管材的外径为9.0mm-14mm。The outer diameter of the pipe is 9.0mm-14mm.
优选地，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。Preferably, the environment shielding layer is a densified corrosion-resistant layer; the densified corrosion-resistant layer includes a ceramic coating and / or a metal coating.
优选地，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； Preferably, 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;
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.
优选地，所述环境屏蔽层为金属层或陶瓷层。Preferably, the environmental shielding layer is a metal layer or a ceramic layer.
优选地，所述金属层为Cr、FeCrAl、FeCrSi、CrNi、CrAl、Ni中的一种或多种制成；Preferably, 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.
优选地，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；Preferably, 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;
所述管材的外径为9.0mm-14mm。The outer diameter of the pipe is 9.0mm-14mm.
优选地，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。Preferably, 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.
优选地，所述核燃料组件的管材为燃料包壳、导向管或热交换管。Preferably, the tube material of the nuclear fuel assembly is a fuel cladding, a guide tube or a heat exchange tube.
本发明还提供一种燃料包壳，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；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;
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.
有益效果Beneficial effect
本发明的有益效果：管材通过金属内层结合SiC纤维增韧SiC复合层形成，适用于燃料包壳、导向管等核燃料组件的管材。其中，SiC纤维增韧SiC复合层作为包壳等管材的主体，起强度支撑作用和在1200℃以上事故工况下的耐蒸汽氧化作用；金属内层的设置解决了包壳等管材的气密性问题，避免裂变气体因为SiC微裂纹而泄露，缓解了包壳与芯块接触的相互作用力（PCMI）和化学反应（PCCI），避免包壳破损；通过环境屏蔽层提高了包壳等管材的的耐水热腐蚀性能，避免溶硅现象。The beneficial effect of the present invention: 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. Among them, the SiC fiber toughened SiC composite layer as the main body of the cladding and other pipes, plays a role of strength support and steam oxidation resistance under accident conditions above 1200 ℃; 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.
本发明适用于事故容错核燃料包壳及组件用途，极大地提高了核反应堆在严重事故工况下维持核燃料组件结构与功能完整性的抗事故能力和安全阈值。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.
附图说明BRIEF DESCRIPTION
下面将结合附图及实施例对本发明作进一步说明，附图中：The present invention will be further described below with reference to the drawings and embodiments. In the drawings:
图1是本发明第一实施例的管材的剖面结构示意图；1 is a schematic cross-sectional structure diagram of a pipe material according to a first embodiment of the present invention;
图2是本发明第二实施例的管材的剖面结构示意图。2 is a schematic cross-sectional structure diagram of a pipe material according to a second embodiment of the present invention.
本发明的实施方式Embodiments of the invention
为了对本发明的技术特征、目的和效果有更加清楚的理解，现对照附图详细说明本发明的具体实施方式。In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific embodiments of the present invention will now be described in detail with reference to the drawings.
如图1所示，本发明第一实施例的核燃料组件的管材10，包括SiC纤维增韧SiC复合层11、设置在SiC纤维增韧SiC复合层11内周的金属内层12、以设置在SiC纤维增韧SiC复合层11外周的环境屏蔽层13。As shown in FIG. 1, 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.
在管材10中，SiC纤维增韧SiC复合层（SiC f/SiC层）11为管材10的主体，起强度支撑作用和在1200℃以上事故工况下的耐蒸汽氧化作用；金属内层12在SiC纤维增韧SiC复合层11的内侧形成金属内管。 In the pipe 10, 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.
该管材10可以是核燃料组件中的燃料包壳、导向管或热交换管等。以管材10为燃料包壳为例，金属内层12一方面起到实现包壳抗渗透性的作用，避免裂变气体因为SiC微裂纹或孔隙而泄露；另一方面缓解芯块-包壳相互作用，通过金属内层12缓解了SiC包壳与芯块接触的相互作用力（PCMI）和化学反应（PCCI），避免包壳破损。The tube 10 may be a fuel cladding, a guide tube, a heat exchange tube, or the like in a nuclear fuel assembly. Taking the tube 10 as a fuel cladding as an example, the metal inner layer 12 on the one hand 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.
金属内层12为致密结构层，选用的材质具备以下特点：具有与SiC匹配的高熔点、中子吸收截面低以及与SiC化学兼容性好。作为选择，金属内层12可以选用铌（Nb）、锆（Zr）、钇（Y）、钽（Ta）、钒（V）、钛（Ti）、铬（Cr）、铁（Fe）、钴（Co）、镍（Ni）中的至少一种单质、合金、或者单质和合金制成。其中Nb为难熔金属，熔点为2477℃，与SiC匹配性更佳；中子吸收截面中，Nb（1.15 barn）＜钼Mo（2.6 barn）<<钨W（18.3 barn）＜钽Ta（20.6 barn）＜＜铪Hf（104 barn）优选地，金属内层12选用Nb、Zr、Y中的一种单质或其合金制成。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. Alternatively, 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. Among them, 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) Preferably, the metal inner layer 12 is made of a single element of Nb, Zr, Y or an alloy thereof.
环境屏蔽层13为包覆在SiC纤维增韧SiC复合层11外周的薄层，对其起到耐水热耐腐蚀的保护作用，避免溶硅现象。在本实施例中，环境屏蔽层13为致密化耐腐蚀层；致密化耐腐蚀层包括陶瓷涂层和/或金属涂层，即可以是陶瓷涂层或金属涂层，也可以是两者结合。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. In this embodiment, 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 .
环境屏蔽层13可以采用熔融挂浆、激光熔覆、物理气相沉积、溅射、热喷涂、等离子喷涂、丝弧涂覆、化学气相沉积、电镀、电泳沉积、无电涂覆以及原子层沉积等方法中至少一种形成。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.
作为选择，陶瓷涂层包括但不限于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相包括但不限于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。金属涂层包括但不限于Cr、FeCrAl、FeCrSi、CrNi、CrAl、Ni中的一种或多种。 Alternatively, 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.
其中，陶瓷涂层优选为SiC陶瓷涂层、CrN陶瓷涂层、Cr 2AlC陶瓷涂层或Ti 3SiC 2陶瓷涂层。金属涂层优选为Cr涂层或FeCrAl涂层。 Among them, 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.
在尺寸上，金属内层12的厚度可为0.1mm-0.5mm，优选为0.1mm-0.3mmSiC纤维增韧SiC复合层11的厚度为0.3mm-1mm，优选为0.3 mm -0.6mm。管材10的外径为9.0mm-14mm，优选为9.5 mm -11mm。In size, 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.
如图2所示，本发明第二实施例的核燃料组件的管材20，包括SiC纤维增韧SiC复合层21、设置在SiC纤维增韧SiC复合层21内周的金属内层22、以设置在SiC纤维增韧SiC复合层21外周的环境屏蔽层23。As shown in FIG. 2, 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.
在管材10中，SiC纤维增韧SiC复合层（SiC f/SiC）21为管材20的主体，起强度支撑作用和在1200℃以上事故工况下的耐蒸汽氧化作用；金属内层22在SiC纤维增韧SiC复合层21的内侧形成金属内管。 In the tube 10, 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.
该管材20可以是核燃料组件中的燃料包壳、导向管或热交换管等。以管材20为燃料包壳为例，金属内层22一方面起到实现包壳抗渗透性的作用，避免裂变气体因为SiC微裂纹或孔隙而泄露；另一方面缓解芯块-包壳相互作用，通过金属内层22缓解了SiC包壳与芯块接触的相互作用力（PCMI）和化学反应（PCCI），避免包壳破损。环境屏蔽层23起到耐水热耐腐蚀的环境屏蔽作用，避免溶硅现象。The tube 20 may be a fuel cladding, a guide tube, a heat exchange tube, or the like in a nuclear fuel assembly. Taking the tube 20 as a fuel cladding as an example, the metal inner layer 22 on the one hand 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.
金属内层22为致密结构层，其可以选用铌（Nb）、锆（Zr）、钇（Y）、钽（Ta）、钒（V）、钛（Ti）、铬（Cr）、铁（Fe）、钴（Co）、镍（Ni）中的至少一种单质、合金、或者单质和合金制成。优选地，金属内层12选用Nb、Zr、Y中的一种单质或其合金制成。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. Preferably, the inner metal layer 12 is made of a single element of Nb, Zr, Y or an alloy thereof.
在本实施例中，环境屏蔽层23为致密结构层，其具体可为金属层或陶瓷层。In this embodiment, the environmental shielding layer 23 is a dense structure layer, which may specifically be a metal layer or a ceramic layer.
金属层为Cr、FeCrAl、FeCrSi、CrNi、CrAl、Ni中的一种或多种制成，优选为Cr或FeCrAl。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；陶瓷层优选为SiC、CrN、Cr 2AlC或Ti 3SiC 2制成。 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 .
环境屏蔽层23可以采用熔融挂浆、激光熔覆、物理气相沉积、溅射、热喷涂、等离子喷涂、丝弧涂覆、化学气相沉积、电镀、电泳沉积、无电涂覆以及原子层沉积等方法中至少一种形成。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.
在尺寸上，金属内层22的厚度可为0.1mm-0.5mm，优选为0.1mm-0.3mm；SiC纤维增韧SiC复合层21的厚度为0.3mm-1mm，优选为0.3 mm -0.6mm；环境屏蔽层23的厚度为0.02mm-0.2mm，优选为0.05mm-0.1mm。管材20的外径为9.0mm-14mm，优选为9.5 mm -11mm。In size, 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.
本发明的核燃料组件的管材中，金属内层12（22）可以采用但不限于轧制、拉拔、卷管、热处理、退火等方式制成。金属内层12（22）在复合SiC f/SiC层11（21）之前，外表面可以经过预氧化处理、预碳化处理、预氮化处理。 In the tube material of the nuclear fuel assembly of the present invention, the inner metal layer 12 (22) can be made by, but not limited to, rolling, drawing, coiling, heat treatment, annealing, etc. Before the metal inner layer 12 (22) is compounded with the SiC f / SiC layer 11 (21), the outer surface may undergo pre-oxidation treatment, pre-carbonization treatment, and pre-nitridation treatment.
SiC纤维增韧SiC复合层11（21）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（CVD）在SiC纤维表面制备界面层，采用先驱体浸渍裂解工艺（PIP）、化学气相浸渍工艺（CVI）、熔融渗透工艺（MI）或者纳米浸渍与瞬时共晶相工艺（NITE）实现SIC基体的致密化烧结，以形成SiC纤维增韧SiC复合层11（21）。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).
以下通过具体实施例对本发明作进一步说明。The present invention will be further described below through specific examples.
实施例1Example 1
采用具有较好成型性与延展性的金属铌经过多次冷轧-热处理的方式制成壁厚0.2mm、外径8.6mm的金属内层管，并对其外表面进行碳化处理。采用高化学计量比的第三代SiC纤维在金属铌管上编织成厚度0.5mm的SiC复合材料骨架，采用化学气相沉积方法在SiC纤维表面制备热解碳PyC界面层，然后采用先驱体浸渍裂解工艺(PIP)，将低熔点聚碳硅烷作为先驱体渗入纤维编织骨架，在常压下高温裂解，使前驱体与纤维发生交联反应，形成致密且结晶度高的SiC f/SiC复合材料层。采用等离子喷涂工艺，在SiC f/SiC复合材料层表面制备厚度0.1mm的金属Cr层，从而制得金属陶瓷型SiC复合材料包壳管。 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. Process (PIP), which uses low-melting polycarbosilane as a precursor to infiltrate the fiber braided skeleton, pyrolysis at high temperature under normal pressure, so that the precursor and fiber undergo cross-linking reaction, forming a dense and highly crystalline SiC f / SiC composite layer . 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.
该金属陶瓷型SiC复合材料包壳管在1200℃下的高温拉伸强度为200MPa，是锆合金的10倍以上；在耐高温氧化性能方面，通过在1200℃高温蒸汽氧化1小时后，该包壳氧化增重仅为0.2mg/cm 2，而没有涂层的锆合金包壳在相同条件下的氧化增重为37 mg/cm 2，说明该包壳有效降低锆合金核燃料包壳高温蒸汽氧化增重2个数量级。 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. In terms of high-temperature oxidation resistance, 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 , while 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.
实施例2Example 2
采用具有较好成型性与延展性的金属锆经过多次冷轧-热处理的方式制成壁厚0.3mm、外径8.8mm的金属内层管，并对其外表面进行预氧化处理。采用高化学计量比的第三代SiC纤维在金属锆管上编织成厚度0.4mm的SiC复合材料骨架，采用化学气相沉积方法在SiC纤维表面制备热解碳PyC界面层，然后采用先驱体浸渍裂解工艺(PIP)，将低熔点聚碳硅烷作为先驱体渗入纤维编织骨架，在常压下高温裂解，使前驱体与纤维发生交联反应，形成致密且结晶度高的SiC f/SiC复合材料层。采用激光熔覆工艺，在SiC f/SiC复合材料层表面制备厚度0.15mm的金属Cr层，从而制得金属陶瓷型SiC复合材料包壳管。 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. Process (PIP), which uses low-melting polycarbosilane as a precursor to infiltrate the fiber braided skeleton, pyrolysis at high temperature under normal pressure, so that the precursor and fiber undergo cross-linking reaction, forming a dense and highly crystalline SiC f / SiC composite layer . Using a laser cladding process, 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.
该金属陶瓷型SiC复合材料包壳管在1200℃下的高温拉伸强度为180MPa；在耐高温氧化性能方面，通过在1200℃高温蒸汽氧化1小时后，该包壳氧化增重仅为0.15 mg/cm 2。 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 .
实施例3Example 3
采用具有较好成型性与延展性的金属钇经过多次冷轧-热处理的方式制成壁厚0.25mm、外径8.7mm的金属内层管，并对其外表面进行预氧化处理。采用高化学计量比的第三代SiC纤维在金属锆管上编织成厚度0.6mm的SiC复合材料骨架，采用化学气相沉积方法在SiC纤维表面制备热解碳PyC界面层，然后采用化学气相浸渍工艺（CVI)使三氯甲基硅烷裂解浸渍沉积形成致密且结晶度高的SiC f/SiC复合材料层。采用磁控溅射工艺，在SiC f/SiC复合材料层表面制备厚度0.05mm的金属FeCrAl层，从而制得金属陶瓷型SiC复合材料包壳管。 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.
该金属陶瓷型SiC复合材料包壳管在1200℃下的高温拉伸强度为230MPa；在耐高温氧化性能方面，通过在1200℃高温蒸汽氧化1小时后，该包壳氧化增重仅为0.12mg/cm 2。 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 .
实施例4Example 4
采用具有较好成型性与延展性的金属铌经过多次冷轧-热处理的方式制成壁厚0.1mm、外径8.5mm的金属内层管，并对其外表面进行氮化处理。采用高化学计量比的第三代SiC纤维在金属锆管上编织成厚度0.7mm的SiC复合材料骨架，采用化学气相沉积方法在SiC纤维表面制备热解碳PyC界面层，然后采用SiC纳米粉体和Y 2O 3-Al 2O 3的低温共晶助烧剂经过纳米浸渍瞬时共晶工艺（NITE），形成致密且结晶度高的SiC f/SiC复合材料层。采用磁控溅射工艺，在SiC f/SiC复合材料层表面制备厚度0.02mm的Cr 2AlC涂层，从而制得金属陶瓷型SiC复合材料包壳管。 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. With the low temperature eutectic sintering aid of Y 2 O 3 -Al 2 O 3 , through nano-impregnation transient eutectic process (NITE), 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.
该金属陶瓷型SiC复合材料包壳管在1200℃下的高温拉伸强度为250MPa；在耐高温氧化性能方面，通过在1200℃高温蒸汽氧化1小时后，该包壳氧化增重仅为0.5 mg/cm 2。 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 .
实施例5Example 5
采用具有较好成型性与延展性的金属钽经过多次冷轧-热处理的方式制成壁厚0.1mm、外径8.5mm的金属内层管，并对其外表面进行碳化处理。采用高化学计量比的第三代SiC纤维在金属锆管上编织成厚度0.7mm的SiC复合材料骨架，采用化学气相沉积方法在SiC纤维表面制备热解碳PyC界面层，然后采用先驱体浸渍裂解工艺(PIP)，将低熔点聚碳硅烷作为先驱体渗入纤维编织骨架，在常压下高温裂解，使前驱体与纤维发生交联反应，形成致密且结晶度高的SiC f/SiC复合材料层。采用化学气相沉积（CVD）工艺，在SiC f/SiC复合材料层表面制备厚度0.02mm的高结晶度致密SiC涂层，从而制得金属陶瓷型SiC复合材料包壳管。 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. Process (PIP), which uses low-melting polycarbosilane as a precursor to infiltrate the fiber braided skeleton, pyrolysis at high temperature under normal pressure, so that the precursor and fiber undergo cross-linking reaction, forming a dense and highly crystalline SiC f / SiC composite layer . 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.
该金属陶瓷型SiC复合材料包壳管在1200℃下的高温拉伸强度为190MPa；在耐高温氧化性能方面，通过在1200℃高温蒸汽氧化1小时后，该包壳氧化增重仅为0.08mg/cm 2。 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 .
可以理解地，本发明的管材不局限于核燃料包壳等核燃料组件、热交换管，还适用于火电厂、化工、医药等领域。Understandably, 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.
以上所述仅为本发明的实施例，并非因此限制本发明的专利范围，凡是利用本发明说明书及附图内容所作的等效结构或等效流程变换，或直接或间接运用在其他相关的技术领域，均同理包括在本发明的专利保护范围内。The above is only an embodiment of the present invention and does not limit the patent scope of the present invention. Any equivalent structure or equivalent process transformation made by the description and drawings of the present invention, or directly or indirectly used in other related technologies In the field, the same reason is included in the patent protection scope of the present invention.

Claims (11)

  1. 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.
  2. 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.
  3. 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.
  4. 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.
  5. 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.
  6. 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.
  7. 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.
  8. 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.
  9. 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.
  10. 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.
  11. 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.
PCT/CN2018/114204 2018-11-06 2018-11-06 Tube for nuclear fuel assembly and fuel cladding WO2020093246A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
PCT/CN2018/114204 WO2020093246A1 (en) 2018-11-06 2018-11-06 Tube for nuclear fuel assembly and fuel cladding

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/CN2018/114204 WO2020093246A1 (en) 2018-11-06 2018-11-06 Tube for nuclear fuel assembly and fuel cladding

Publications (1)

Publication Number Publication Date
WO2020093246A1 true WO2020093246A1 (en) 2020-05-14

Family

ID=70611595

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/CN2018/114204 WO2020093246A1 (en) 2018-11-06 2018-11-06 Tube for nuclear fuel assembly and fuel cladding

Country Status (1)

Country Link
WO (1) WO2020093246A1 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112750538A (en) * 2020-12-31 2021-05-04 中核北方核燃料元件有限公司 Silicon carbide composite material reinforced zirconium cladding tube
WO2023070067A1 (en) * 2021-10-21 2023-04-27 Westinghouse Electric Company Llc Annular nuclear fuel rod

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105405474A (en) * 2015-11-02 2016-03-16 西北工业大学 Structure and preparation method of nuclear fuel cladding tube with crack expansion resisting capability
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

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105405474A (en) * 2015-11-02 2016-03-16 西北工业大学 Structure and preparation method of nuclear fuel cladding tube with crack expansion resisting capability
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
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

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112750538A (en) * 2020-12-31 2021-05-04 中核北方核燃料元件有限公司 Silicon carbide composite material reinforced zirconium cladding tube
WO2023070067A1 (en) * 2021-10-21 2023-04-27 Westinghouse Electric Company Llc Annular nuclear fuel rod
TWI834347B (en) * 2021-10-21 2024-03-01 美商西屋電器公司 Annular nuclear fuel rod

Similar Documents

Publication Publication Date Title
Duan et al. Current status of materials development of nuclear fuel cladding tubes for light water reactors
WO2019052315A1 (en) Fuel cladding and fuel assembly
US9982350B2 (en) Multilayer composite fuel clad system with high temperature hermeticity and accident tolerance
JP6140701B2 (en) Improved multi-layer tube made of ceramic matrix composite, resulting nuclear fuel cladding and related manufacturing processes
EP3117440B1 (en) Double-sealed fuel rod end plug for ceramic-containing cladding
JP7367020B2 (en) Coating and surface modification to calm SiC cladding during light water reactor operation
CN112164479B (en) High-temperature steam corrosion resistant coating for zirconium alloy cladding tube
CN105706176A (en) A sic matrix fuel cladding tube with spark plasma sintered end plugs
WO2014199459A1 (en) Tubular body and method for manufacturing tubular body
US10593434B2 (en) Ceramic reinforced zirconium alloy nuclear fuel cladding with intermediate oxidation resistant layer
JP2008501977A (en) Multilayer ceramic tubes used for fuel containment barriers in nuclear power plants
KR101526305B1 (en) Multi-layered metal-ceramic composite nuclear fuel cladding tube
CN105405474A (en) Structure and preparation method of nuclear fuel cladding tube with crack expansion resisting capability
JP6850209B2 (en) Joining member, joining structure using it, and manufacturing method of joining member
WO2020093246A1 (en) Tube for nuclear fuel assembly and fuel cladding
JP6632931B2 (en) Structural member and manufacturing method thereof, fuel rod, fuel channel box, water rod, fuel assembly
US10217533B2 (en) Fuel rod cladding and methods for making and using same
KR20240014490A (en) Random grain structure coating applied by cathode arc on zirconium alloy nuclear fuel cladding
Jung et al. Metal-ceramic hybrid fuel cladding tubes aiming at suppressed hydrogen release properties
JP7350254B2 (en) Fuel rod with end plug attached
张腾飞 et al. High Temperature Steam Oxidation Resistance of Mo/Al/Cr Composite Coating on Zirconium Alloy
Park et al. Development of advanced claddings for suppressing the hydrogen emission in accident conditions. Development of advanced claddings for suppressing the hydrogen emission in the accident condition
JP2019215301A (en) Fuel cladding tube and method for manufacturing fuel cladding tube
RU2393558C2 (en) Micro-fuel elements of nuclear reactor with double-layer protective cladding of fuel micro-sphere

Legal Events

Date Code Title Description
121 Ep: the epo has been informed by wipo that ep was designated in this application

Ref document number: 18939234

Country of ref document: EP

Kind code of ref document: A1

NENP Non-entry into the national phase

Ref country code: DE

122 Ep: pct application non-entry in european phase

Ref document number: 18939234

Country of ref document: EP

Kind code of ref document: A1

32PN Ep: public notification in the ep bulletin as address of the adressee cannot be established

Free format text: NOTING OF LOSS OF RIGHTS PURSUANT TO RULE 112(1) EPC (EPO FORM 1205A DATED 24.09.2021)

122 Ep: pct application non-entry in european phase

Ref document number: 18939234

Country of ref document: EP

Kind code of ref document: A1