CN106128532B - A kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and preparation method thereof - Google Patents
A kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and preparation method thereof Download PDFInfo
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- CN106128532B CN106128532B CN201610417182.1A CN201610417182A CN106128532B CN 106128532 B CN106128532 B CN 106128532B CN 201610417182 A CN201610417182 A CN 201610417182A CN 106128532 B CN106128532 B CN 106128532B
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- titanium alloy
- zircaloy
- pipe
- tube
- composite tube
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
- C22F1/02—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working in inert or controlled atmosphere or vacuum
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
- C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
- C22F1/18—High-melting or refractory metals or alloys based thereon
- C22F1/183—High-melting or refractory metals or alloys based thereon of titanium or alloys based thereon
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
- C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
- C22F1/18—High-melting or refractory metals or alloys based thereon
- C22F1/186—High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon
-
- 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
Abstract
The invention discloses a kind of Reactor fuel element cladding zircaloy titanium alloy composite tubes and preparation method thereof.The multiple tube includes the internal layer tubing and outer layer tubing of metallurgical binding, and internal layer tubing is zircaloy, and outer layer tubing is titanium alloy, is metallurgical bonding layer between zirconium alloy tube and titanium alloy pipe.The element that metallurgical bonding layer contains comes from internal layer tubing and outer layer tubing.Compared with zirconium alloy cladding pipe, the zircaloy titanium alloy composite tube of the present invention is dissimilar metal multiple tube, it is with more excellent water-fast side corrosive nature and preferable heat resistance, the ability of the anti-LOCA accident of fuel rod can be improved, be suitable for water cooled nuclear reactor compared with the fuel rod clad pipe under high burnup or under higher temperature.
Description
Technical field
The present invention relates to Reactor fuel element cladding fields, can be used as water cooled nuclear reactor compared with high burnup more particularly, to one kind
Fuel rod clad pipe under lower or higher temperature.Particularly, the present invention relates to improvement corrosion resistant is shown in water cooled nuclear reactor
The ability of the anti-LOCA accident of fuel rod can be improved in the fuel tube of corrosion energy and preferable heat resistance, this cladding tubes.
Background technology
Zircaloy since thermal neutron absorption cross section is small, thermal conductivity is high, good mechanical property, and with good processing performance with
And same UO2Compatibility is good, especially also has good etch resistant properties and enough heat resistances to high-temperature water, high-temperature vapor, because
This is widely used as the cladding materials and core structural material of water cooling power reactor.
Currently, although addible alloying element is limited by thermal neutron absorption cross section size in zircaloy, but still
The zircaloy for foring a variety of series, summing up mainly has Zr-Sn systems, Zr-Nb systems and Zr-Sn-Nb systems three categories.Zr-Sn
Owner will have Zr-2 alloys, Zr-4 alloys and low tin Zr-4 alloys etc., Zr-Nb systems have Zr-2.5%Nb alloys (herein unless
Illustrate, all the components are mass percent), Zr-1%Nb alloys and M5 alloys, Zr-Sn-Nb systems include the western room in the U.S.
The ZIRLO alloys of company, the NDA alloys of Japan, the E635 alloys of Russia and the N18 alloys in China, N36 alloys etc..
In order to further increase economy and the safety of nuclear power, nuclear fuel element is increasingly to high burnup, long circulating side
To development, this constantly proposes zirconium alloy cladding material new requirement and challenge.For this purpose, countries in the world never stopped zirconium
The paces of alloy research development.
First generation zircaloy such as routine Zr-4 alloy burnups can only achieve 30GWd/tU, and optimization Zr-4 alloy burnups are reachable
40-50GWd/tU；
Second generation zircaloy is developed since the seventies in last century both at home and abroad, for mainly having for presurized water reactor：E635 alloys,
ZIRLO alloys and M5 alloys etc..The approved fuel-assembly burn-up of ZIRLO alloys is 60GWd/tU, and optimization ZIRLO alloys are criticized
Accurate fuel-assembly burn-up is up to 70GWd/tU；The approved fuel-assembly burn-up of M5 alloys is 52-62GWd/tU, Germany's approval
M5 alloy fuel component burnups reach 70GWd/tU.
Currently, still new zirconium alloy cladding material is being continually developed both at home and abroad, to improve its corrosion resistance, inhale hydrogen
Energy, mechanical property, Flouride-resistani acid phesphatase growth performance and Flouride-resistani acid phesphatase croop property, wherein corrosion resistance and hydrogen sucking function be zircaloy most
Performance that is crucial and being most also easy to produce variation.
After Fukushima, Japan nuclear accident in 2011, to the ability of the anti-LOCA accident of fuel rod, more stringent requirements are proposed.Currently,
Those skilled in the art attempt to find a kind of fuel rod clad material of anti-LOCA accident.
Invention content
In view of the deficiency of existing zirconium alloy cladding pipe, technical problem to be solved by the invention is to provide a kind of high temperature resistant height
The New-type fuel stick cladding tubes of water corrosion are pressed, there is more excellent water-fast side corrosive nature and preferable heat resistance, it can
Improve the ability of the anti-LOCA accident of fuel rod.
To achieve the above object, the present invention provides a kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and its systems
Preparation Method, specifically, technical solution provided by the invention are as follows：
A kind of preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube, includes the following steps：
A) zircaloy blank is prepared into zircaloy pipe by processing；
B) titanium alloy blank is prepared into titanium alloy pipe by processing；
C) it by the assembly of titanium alloy pipe outside zircaloy pipe, is put into electron beam weldering case and vacuumizes, then to titanium alloy
The upper surface and lower face of pipe and zircaloy pipe carry out electron beam welding, make the contact of titanium alloy pipe and zircaloy pipe
Gap between face keeps vacuum, obtains extrusion tube blank；
D) extrusion tube blank is wrapped into interior jacket and outer jacket, heated under vacuum or under inert gas shielding, then
It is squeezed using extruder, obtains rolling pipe；
E) after being cleaned rolling pipe, zircaloy titanium is obtained by rolling mill practice for jacket and outer jacket in removing
Alloy composite pipe has metallurgical bonding layer in zircaloy titanium alloy composite tube between zirconium alloy pipe and titanium alloy tube.
Preferably, the zircaloy blank in step a includes pure zirconium and zirconium-base alloy, and zirconium-base alloy includes Zr-Sn systems, Zr-
Nb systems or Zr-Sn-Nb systems alloy.
Preferably, the titanium alloy blank in step b includes pure titanium and titanium-base alloy, and titanium-base alloy includes alpha titanium alloy, alpha+beta
Titanium alloy or beta-titanium alloy.
Preferably, before step c by zircaloy pipe and titanium alloy pipe is machined out and surface clean, make contact surface
Keep cleaning.
Preferably, it is evacuated to less than 3 × 10 in step c-3Pa。
Preferably, the heating temperature in step d is 700 DEG C -1250 DEG C.
A kind of Reactor fuel element cladding zircaloy titanium alloy composite tube, multiple tube include the internal layer tubing of metallurgical binding and outer
Layer tubing, internal layer tubing are zircaloy, and outer layer tubing is titanium alloy, multiple tube further include be located at internal layer tubing and outer layer tubing it
Between metallurgical bonding layer, the element that metallurgical bonding layer contains come from internal layer tubing and outer layer tubing.
Preferably, the element that metallurgical bonding layer contains include Zr, Ti, Al, V, Cr, Mn, Cu, Fe, Mo, Ni, Sn, Co, Nb,
It is one or more in the elements such as Si, C, O, N, S, Be.
Preferably, the thickness of internal layer tubing is 0.05mm~0.95mm, and the thickness of outer layer tubing is 0.05mm~0.70mm,
The thickness of metallurgical bonding layer is 0.001mm~0.20mm.
A kind of nuclear fuel rod using Reactor fuel element cladding zircaloy titanium alloy composite tube, nuclear fuel rod include cartridge
Body and involucrum.Involucrum is zircaloy titanium alloy composite tube, is followed successively by zircaloy, metallurgical bonding layer and titanium alloy from inside to outside, is fired
Expect that core is arranged in zircaloy titanium alloy composite tube.
Due to the adoption of the above technical solution, the present invention has the characteristics that compared with zirconium alloy cladding tubing：
First, the zircaloy titanium alloy composite tube obtained through the invention is dissimilar metal multiple tube, anti-water side corrosion
Performance is better than zirconium alloy cladding pipe.The present invention passes through metallurgical junction in the outside of the cladding nuclear fuels zirconium alloy pipe of the prior art
Conjunction increases one layer of titanium alloy layer, is closed since corrosion resistance of the titanium alloy material in high temperature and pressure aqueous medium is better than zirconium
Gold has slower oxidation rate especially under steam condition, avoids zirconium alloy cladding pipe and occur at high temperature due to mistake
Embrittlement failure caused by degree oxidation, therefore, multiple tube can improve the water-fast side corrosive nature of fuel rod clad pipe.
Second, the dissimilar metal multiple tube obtained through the invention, heat resistance is better than zirconium alloy cladding pipe.The present invention
The zircaloy titanium alloy composite tube is metallurgical bonding layer between zirconium alloy tube and titanium alloy pipe.The metallurgical bonding layer
Cementation is played, makes to combine closely between zircaloy and titanium alloy very close to each other, since the elevated temperature strength of titanium alloy is better than
The reason of zircaloy so that the heat resistance of multiple tube is better than zirconium alloy tube.
Third, the dissimilar metal multiple tube obtained through the invention have good heat conductivility.Due in multiple tube
It is metallurgical binding between zirconium alloy tube and titanium alloy pipe, presence very close to each other between two kinds of tubing, therefore, multiple tube has
Good heat conductivility.
Therefore, compared with zirconium alloy cladding pipe, zircaloy titanium alloy dissimilar metal multiple tube of the invention has more excellent
Different water-fast side corrosive nature and preferable heat resistance, can ensure that the structural intergrity of fuel rod, can be improved at relatively high temperatures
The ability of the anti-LOCA accident of fuel rod is suitable for water cooled nuclear reactor compared with the fuel rod clad under high burnup or under higher temperature
Pipe.
The method of the present invention and the technique effect of generation are described further below with reference to attached drawing, to be fully understood from
The purpose of the present invention, feature and effect.
Description of the drawings
Fig. 1 is the multiple tube sectional view of presently preferred embodiments of the present invention.
Fig. 2 is the extrusion tube blank end assembling schematic diagram of presently preferred embodiments of the present invention.
Fig. 3 is the schematic diagram of the metallurgical bonding layer of the multiple tube of presently preferred embodiments of the present invention.
Specific implementation mode
It is the multiple tube sectional view of present pre-ferred embodiments as shown in Figure 1, multiple tube includes internal layer tubing 1 and outer tube
Material 2.Wherein internal layer tubing 1 uses zircaloy, outer layer tubing 2 to use titanium alloy.Multiple tube further includes being located at internal layer tubing 1 and outer
Metallurgical bonding layer 3 between layer tubing 2, contained element come from internal layer tubing 1 and outer layer tubing 2.
The zircaloy that this preferred embodiment uses is preferably Zr-4 alloys, and Zr-4 alloy pipe thickness is 0.35~
0.55mm；Titanium alloy is preferably Ti-6Al-4V titanium alloys, and titanium alloy pipe thickness is 0.15-0.35mm；Metallurgical binding layer thickness
For 0.01mm-0.1mm.The thickness of zircaloy titanium alloy composite tube is 0.50mm-0.65mm, outer diameter 8.0mm-12mm, length
For 1.0m-6.0m.
The preparation process of the zircaloy titanium alloy dissimilar metal multiple tube of present pre-ferred embodiments and steps are as follows：
(1) by processing, Zr-4 alloy blanks are prepared into Zr-4 alloy pipe stocks；
(2) by processing, Ti-6Al-4V titanium alloy blanks are prepared into Ti-6Al-4V titanium alloy pipes；
(3) two kinds of pipes are machined out and surface clean, contact surface is made to keep cleaning；
(4) process two kinds of pipes are assembled, as shown in Fig. 2, titanium alloy pipe (outer layer tubing 2) is assemblied in zirconium
Alloy pipe stock (internal layer tubing 1) outside, is put into electron beam weldering case and vacuumizes, vacuum is less than 3 × 10-3Pa, then to pipe end face
Electron beam welding is carried out, so that the gap between the two contact surface is kept vacuum, obtains extrusion tube blank.
(5) extrusion tube blank is wrapped into inside and outside jacket, is heated under vacuum at 1150 DEG C, it is then enterprising in extruder
Row squeezes, and obtains rolling pipe.
(6) inside and outside jacket is removed, after rolling pipe is cleaned, multiple tube is obtained by rolling mill practice.Such as Fig. 3
It is shown, one layer of metallurgical bonding layer 3 is formed wherein between zirconium alloy pipe (internal layer tubing 1) and titanium alloy tube (outer layer tubing 2).
Since the Ti-6Al-4V titanium alloys of outer layer have excellent corrosion resistance, especially in high temperature and pressure aqueous medium
The corrosion resistance for exhibiting improvements over zircaloy can slow down high-temperature oxydation when LOCA accident occurs for reactor；Meanwhile Ti-
The elevated temperature strength of 6Al-4V titanium alloys is better than zircaloy, and therefore, the heat resistance of the multiple tube is better than zircaloy.Therefore, with
Zirconium alloy cladding pipe is compared, and dissimilar metal multiple tube of the invention has more excellent water-fast side corrosive nature and higher heat
The ability of the anti-LOCA accident of fuel rod can be improved in epistasis, is suitable for nuclear reactor compared with the combustion under high burnup or under higher temperature
Charge bar cladding tubes.
The preferred embodiment of the present invention has been described in detail above.It should be appreciated that the ordinary skill of this field is without wound
The property made labour, which according to the present invention can conceive, makes many modifications and variations.Therefore, all technician in the art
Pass through the available technology of logical analysis, reasoning, or a limited experiment on the basis of existing technology under this invention's idea
Scheme, all should be in the protection domain being defined in the patent claims.
Claims (8)
1. a kind of preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube, which is characterized in that include the following steps：
A) zircaloy blank is prepared into zircaloy pipe by processing；
B) titanium alloy blank is prepared into titanium alloy pipe by processing；
C) it by the assembly of titanium alloy pipe outside zircaloy pipe, is put into electron beam weldering case and vacuumizes, then to titanium alloy pipe
Carry out electron beam welding with the upper surface of zircaloy pipe and lower face, make the contact surface of titanium alloy pipe and zircaloy pipe it
Between gap keep vacuum, obtain extrusion tube blank；
D) extrusion tube blank is wrapped into interior jacket and outer jacket, heated under vacuum or under inert gas shielding, heating temperature
For：It 1150-1250 DEG C, is then squeezed using extruder, obtains rolling pipe；
E) after being cleaned rolling pipe, zircaloy titanium alloy is obtained by rolling mill practice for jacket and outer jacket in removing
Multiple tube has metallurgical bonding layer in zircaloy titanium alloy composite tube between zirconium alloy pipe and titanium alloy tube.
2. the preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube as described in claim 1, in wherein step a
The zircaloy blank include pure zirconium and zirconium-base alloy, zirconium-base alloy includes that Zr-Sn systems, Zr-Nb systems or Zr-Sn-Nb systems close
Gold.
3. the preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube as described in claim 1, in wherein step b
The titanium alloy blank include pure titanium and titanium-base alloy, titanium-base alloy includes alpha titanium alloy, alpha+beta titanium alloys or beta-titanium alloy.
4. the preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube as described in claim 1, wherein in step c
It is preceding by zircaloy pipe and titanium alloy pipe is machined out and surface clean, so that contact surface is kept cleaning.
5. the preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube as described in claim 1, in wherein step c
It is evacuated to and is less than 3 × 10-3Pa。
6. a kind of Reactor fuel element cladding zircaloy titanium alloy composite tube, which is characterized in that the multiple tube includes metallurgical binding
Internal layer tubing and outer layer tubing, the internal layer tubing be zircaloy, the outer layer tubing is titanium alloy, and the multiple tube also wraps
The metallurgical bonding layer between the internal layer tubing and the outer layer tubing is included, the element that the metallurgical bonding layer contains comes from
The internal layer tubing and the outer layer tubing, wherein the thickness of the inner tube material is 0.05mm~0.95mm, the outer tube
The thickness of material is 0.05mm~0.70mm, and the thickness of the metallurgical bonding layer is more than 0.01mm and to be no more than 0.20mm.
7. Reactor fuel element cladding zircaloy titanium alloy composite tube as claimed in claim 6, wherein the metallurgical bonding layer contains
Some elements include one kind in the elements such as Zr, Ti, Al, V, Cr, Mn, Cu, Fe, Mo, Ni, Sn, Co, Nb, Si, C, O, N, S, Be
Or it is a variety of.
8. a kind of nuclear fuel rod using the Reactor fuel element cladding zircaloy titanium alloy composite tube as described in claim 6-7,
It is characterized in that, the nuclear fuel rod includes fuel core and involucrum, the involucrum is zircaloy titanium alloy composite tube, from it is interior to
Outer to be followed successively by zircaloy, metallurgical bonding layer and titanium alloy, the fuel core is arranged in the zircaloy titanium alloy composite tube.
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| CN201610417182.1A CN106128532B (en) | 2016-06-12 | 2016-06-12 | A kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and preparation method thereof |
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| CN201610417182.1A CN106128532B (en) | 2016-06-12 | 2016-06-12 | A kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and preparation method thereof |
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| CN107116339B (en) * | 2017-05-03 | 2019-12-03 | 中国核动力研究设计院 | A kind of zirconium alloy cladding tubing preparation process |
| KR20230113828A (en) * | 2017-07-19 | 2023-08-01 | 테라파워, 엘엘씨 | Fuel-cladding chemical interaction resistant nuclear fuel elements and methods of manufacturing the same |
| CN108080436A (en) * | 2017-11-13 | 2018-05-29 | 安徽天潭金属材料有限公司 | A kind of production method of new-type compound aluminum tube |
| JP6999810B2 (en) * | 2017-11-14 | 2022-01-19 | コリア アトミック エナジー リサーチ インスティテュート | Zirconium alloy cladding tube with improved high temperature oxidation resistance and its manufacturing method |
| CN108231214B (en) * | 2017-12-07 | 2020-12-08 | 广东核电合营有限公司 | Composite tube for nuclear fuel assembly and method for manufacturing same |
| CN110871327B (en) * | 2018-09-03 | 2021-07-30 | 核工业西南物理研究院 | Fusion reactor high-heat-load multilayer composite pipe and manufacturing method thereof |
| US20200161010A1 (en) * | 2018-11-20 | 2020-05-21 | Westinghouse Electric Company Llc | Coatings and Surface Modifications to Mitigate SiC Cladding During Operation in Light Water Reactors |
| CN114261153B (en) * | 2021-10-18 | 2023-09-05 | 贵州盛航云集科技有限公司 | Metal or alloy composite structure and preparation method and application thereof |
| CN114015959A (en) * | 2021-11-08 | 2022-02-08 | 上海核工程研究设计院有限公司 | Wear-resistant and oxidation-resistant composite coating for zirconium alloy cladding pipe of nuclear power plant and preparation method thereof |
| CN115171920A (en) * | 2022-06-14 | 2022-10-11 | 中国核动力研究设计院 | Double-layer composite cladding tube for nuclear fuel, nuclear fuel and preparation method |
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Effective date of registration: 20210420 Address after: 200233 Shanghai city Xuhui District Hong Cao Road No. 29 Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Patentee after: National Nuclear Uranium Industry Development Co.,Ltd. Address before: 200233 Shanghai city Xuhui District Hong Cao Road No. 29 Patentee before: Shanghai Nuclear Engineering Research & Design Institute |
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| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Patentee after: National Nuclear Uranium Industry Development Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Patentee before: National Nuclear Uranium Industry Development Co.,Ltd. |