CN106128532A - 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
- Publication number
- CN106128532A CN106128532A CN201610417182.1A CN201610417182A CN106128532A CN 106128532 A CN106128532 A CN 106128532A CN 201610417182 A CN201610417182 A CN 201610417182A CN 106128532 A CN106128532 A CN 106128532A
- Authority
- CN
- China
- Prior art keywords
- titanium alloy
- zircaloy
- pipe
- tube
- composite tube
- Prior art date
- Legal status (The legal status 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 status listed.)
- Granted
Links
Classifications
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Metallurgy (AREA)
- Mechanical Engineering (AREA)
- Materials Engineering (AREA)
- Crystallography & Structural Chemistry (AREA)
- Thermal Sciences (AREA)
- Organic Chemistry (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Pressure Welding/Diffusion-Bonding (AREA)
Abstract
The invention discloses a kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and preparation method thereof.This multiple tube includes internal layer tubing and the 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 is 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 has the most excellent water-fast side corrosive nature and preferable heat resistance, the ability of the anti-LOCA accident of fuel rod can be improved, it is adaptable to water cooled nuclear reactor is 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 field, especially relate to one and can be used as water cooled nuclear reactor relatively high burnup
Fuel rod clad pipe down or under higher temperature.Especially, the present invention relates in water cooled nuclear reactor, show improvement corrosion resistant
The fuel tube of erosion performance and preferably heat resistance, this cladding tubes can improve the ability of the anti-LOCA accident of fuel rod.
Background technology
Zircaloy owing to thermal neutron absorption cross section is little, thermal conductivity is high, good mechanical property, have again good processing characteristics with
And same UO2The compatibility is good, especially also has good etch resistant properties and enough heat resistances to high-temperature water, high-temperature vapor, because of
This cladding materials being widely used as water-cooled power reactor and core structural material.
At present, although addible alloying element is limited by thermal neutron absorption cross section size in zircaloy, but still
Define the zircaloy of multiple series, sum up and mainly have Zr-Sn system, Zr-Nb system and Zr-Sn-Nb system three major types.Zr-Sn
Owner's Zr-2 to be had alloy, Zr-4 alloy and low stannum Zr-4 alloy etc., Zr-Nb system have Zr-2.5%Nb alloy (herein unless
Special instruction, all the components is mass percent), Zr-1%Nb alloy and M5 alloy, Zr-Sn-Nb system includes the western room of the U.S.
The ZIRLO alloy of company, NDA alloy, Muscovite E635 alloy and the N18 alloy of China, the N36 alloy etc. of Japan.
In order to improve economy and the safety of nuclear power further, nuclear fuel element is increasingly to high burnup, long circulating side
To development, this constantly proposes new requirement and challenge to zirconium alloy cladding material.To this end, countries in the world did not the most stop zirconium
The paces of alloy research development.
First generation zircaloy can only achieve 30GWd/tU such as conventional Zr-4 alloy burnup, optimize Zr-4 alloy burnup up to
40-50GWd/tU；
Second filial generation zircaloy has been developed both at home and abroad, mainly having for presurized water reactor since the seventies in last century: E635 alloy,
ZIRLO alloy and M5 alloy etc..The approved fuel-assembly burn-up of ZIRLO alloy is 60GWd/tU, optimizes ZIRLO alloy and is criticized
Accurate fuel-assembly burn-up is up to 70GWd/tU；The approved fuel-assembly burn-up of M5 alloy is 52-62GWd/tU, Germany's approval
M5 alloy fuel assembly burnup reach 70GWd/tU.
At present, the most still continually developing new zirconium alloy cladding material, to improve its decay resistance, to inhale hydrogen
Energy, mechanical property, Flouride-resistani acid phesphatase growth performance and Flouride-resistani acid phesphatase croop property, wherein decay resistance and hydrogen sucking function be zircaloy
Crucial and be easily generated most the performance of change.
After Fukushima, Japan nuclear accident in 2011, the ability of LOCA accident anti-to fuel rod is had higher requirement.At present,
Those skilled in the art attempt to find the fuel rod clad material of a kind of anti-LOCA accident.
Summary of the invention
In view of the deficiency of existing zirconium alloy cladding pipe, the technical problem to be solved is to provide a kind of high temperature resistant height
The New-type fuel rod cladding tubes of setting-out dielectric corrosion, has the most excellent water-fast side corrosive nature and preferable heat resistance, can
Improve the ability of the anti-LOCA accident of fuel rod.
For achieving the above object, the invention provides a kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and system thereof
Preparation Method, specifically, the technical scheme that the present invention provides is as follows:
The preparation method of a kind of Reactor fuel element cladding zircaloy titanium alloy composite tube, comprises the following steps:
A) by zircaloy blank through processing, it is prepared as zircaloy pipe；
B) by titanium alloy blank through processing, it is prepared as titanium alloy pipe；
C) titanium alloy pipe is assemblied in outside zircaloy pipe, puts into electron beam weldering case evacuation, then to titanium alloy
Pipe and the upper surface of zircaloy pipe and lower surface carry out electron beam welding, make titanium alloy pipe and the contact of zircaloy pipe
Gap between face keeps vacuum, obtains extrusion tube blank；
D) extrusion tube blank is wrapped interior jacket and outer jacket, under vacuum or heat, then under inert gas shielding
Utilize extruder to extrude, obtain rolling pipe；
E) jacket and outer jacket in removing, after being carried out by rolling pipe, obtain zircaloy titanium by rolling mill practice
Alloy composite pipe, has metallurgical bonding layer between zirconium alloy pipe and titanium alloy tube in zircaloy titanium alloy composite tube.
Preferably, the zircaloy blank in step a includes pure zirconium and zirconium-base alloy, and zirconium-base alloy includes Zr-Sn system, Zr-
Nb system or Zr-Sn-Nb system 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, zircaloy pipe and titanium alloy pipe are machined out and surface clean, make contact surface
Keep cleaning.
Preferably, step c is evacuated to less than 3 × 10-3Pa。
Preferably, the heating-up 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 includes that the internal layer tubing of metallurgical binding is with outer
Layer tubing, internal layer tubing is zircaloy, and outer layer tubing is titanium alloy, multiple tube also include being positioned at internal layer tubing and outer layer tubing it
Between metallurgical bonding layer, the element that metallurgical bonding layer contains is 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,
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 includes 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, combustion
Material core body is arranged in zircaloy titanium alloy composite tube.
Due to the employing of technique scheme, the present invention has the following characteristics that compared with zirconium alloy cladding tubing
First, the zircaloy titanium alloy composite tube obtained by the present invention is dissimilar metal multiple tube, its anti-water side corrosion
Performance is better than zirconium alloy cladding pipe.The present invention, in the outside of the cladding nuclear fuels zirconium alloy pipe of prior art, passes through metallurgical junction
Conjunction adds one layer of titanium alloy layer, closes owing to titanium alloy material corrosion resistance in High Temperature High Pressure aqueous medium is better than zirconium
Gold, particularly have slower oxidation rate under steam condition, it is to avoid zirconium alloy cladding pipe at high temperature occurs due to mistake
The brittle inefficacy that degree aoxidizes and causes, therefore, multiple tube can improve the water-fast side corrosive nature of fuel rod clad pipe.
Second, the dissimilar metal multiple tube obtained by the present invention, its heat resistance is better than zirconium alloy cladding pipe.The present invention
Described zircaloy titanium alloy composite tube, is metallurgical bonding layer between zirconium alloy tube and titanium alloy pipe.This metallurgical bonding layer
Play cementation, make to combine closely between zircaloy and titanium alloy very close to each other, owing to 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.
3rd, the dissimilar metal multiple tube obtained by the present invention, there is good heat conductivility.Due in multiple tube
Being metallurgical binding between zirconium alloy tube and titanium alloy pipe, existence very close to each other between two kinds of tubing, therefore, multiple tube has
Good heat conductivility.
Therefore, compared with zirconium alloy cladding pipe, the zircaloy titanium alloy dissimilar metal multiple tube of the present invention has the most excellent
Different water-fast side corrosive nature and preferable heat resistance, can ensure that the structural intergrity of fuel rod at relatively high temperatures, can improve
The ability of the anti-LOCA accident of fuel rod, it is adaptable to water cooled nuclear reactor is compared with the fuel rod clad under high burnup or under higher temperature
Pipe.
Below with reference to accompanying drawing, the method for the present invention and the technique effect of generation are described further, to be fully understood from
The purpose of the present invention, feature and effect.
Accompanying drawing explanation
Fig. 1 is the multiple tube profile 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.
Detailed description of the invention
Being illustrated in figure 1 the multiple tube profile of present pre-ferred embodiments, 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 also includes being positioned at internal layer tubing 1 with outer
Metallurgical bonding layer 3 between layer tubing 2, element contained by it is from internal layer tubing 1 and outer layer tubing 2.
This preferred embodiment use zircaloy be preferably Zr-4 alloy, Zr-4 alloy pipe thickness be 0.35～
0.55mm；Titanium alloy is preferably Ti-6Al-4V titanium alloy, 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, and external diameter is 8.0mm-12mm, length
For 1.0m-6.0m.
Preparation process and the step of the zircaloy titanium alloy dissimilar metal multiple tube of present pre-ferred embodiments are as follows:
(1) by processing, Zr-4 alloy blank is prepared as Zr-4 alloy pipe stock；
(2) by processing, Ti-6Al-4V titanium alloy blank is prepared as Ti-6Al-4V titanium alloy pipe；
(3) two kinds of pipes are machined out and surface clean, make contact surface keep cleaning；
(4) process two kinds of pipes are assembled, as in figure 2 it is shown, titanium alloy pipe (outer layer tubing 2) is assemblied in zirconium
Alloy pipe stock (internal layer tubing 1) outward, puts into electron beam weldering case evacuation, and vacuum is less than 3 × 10-3Pa, then to pipe end face
Carry out electron beam welding, make the gap between both contact surfaces keep vacuum, obtain extrusion tube blank.
(5) extrusion tube blank is wrapped inside and outside jacket, under vacuum 1150 DEG C of heating, then enterprising at extruder
Row extruding, obtains rolling pipe.
(6) remove inside and outside jacket, after being carried out by rolling pipe, obtain multiple tube by rolling mill practice.Such as Fig. 3
Shown in, wherein form one layer of metallurgical bonding layer 3 between zirconium alloy pipe (internal layer tubing 1) and titanium alloy tube (outer layer tubing 2).
Owing to the Ti-6Al-4V titanium alloy of outer layer has the corrosion resistance of excellence, particularly in High Temperature High Pressure aqueous medium
Exhibit improvements over the corrosion resistance of zircaloy, high-temperature oxydation can be slowed down when reactor generation LOCA accident；Meanwhile, Ti-
The elevated temperature strength of 6Al-4V titanium alloy is better than zircaloy, and therefore, the heat resistance of this multiple tube is better than zircaloy.Therefore, with
Zirconium alloy cladding pipe is compared, and the dissimilar metal multiple tube of the present invention has the most excellent water-fast side corrosive nature and higher heat
Epistasis, can improve the ability of the anti-LOCA accident of fuel rod, it is adaptable to nuclear reactor is compared with the combustion under high burnup or under higher temperature
Charge bar cladding tubes.
The preferred embodiment of the present invention described in detail above.Should be appreciated that the ordinary skill of this area is without wound
The property made work just can make many modifications and variations according to the design of the present invention.Therefore, all technical staff in the art
The most on the basis of existing technology by the available technology of logical analysis, reasoning, or a limited experiment
Scheme, all should be in the protection domain being defined in the patent claims.
Claims (10)
1. the preparation method of a Reactor fuel element cladding zircaloy titanium alloy composite tube, it is characterised in that comprise the following steps:
A) by zircaloy blank through processing, it is prepared as zircaloy pipe；
B) by titanium alloy blank through processing, it is prepared as titanium alloy pipe；
C) titanium alloy pipe is assemblied in outside zircaloy pipe, puts into electron beam weldering case evacuation, then to titanium alloy pipe
Carry out electron beam welding with upper surface and the lower surface of zircaloy pipe, make titanium alloy pipe and zircaloy pipe contact surface it
Between gap keep vacuum, obtain extrusion tube blank；
D) extrusion tube blank is wrapped interior jacket and outer jacket, under vacuum or heat under inert gas shielding, then utilize
Extruder extrudes, and obtains rolling pipe；
E) jacket and outer jacket in removing, after being carried out by rolling pipe, obtain zircaloy titanium alloy by rolling mill practice
Multiple tube, has metallurgical bonding layer between zirconium alloy pipe and titanium alloy tube in zircaloy titanium alloy composite tube.
2. the preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube as claimed in claim 1, wherein in step a
Described zircaloy blank include pure zirconium and zirconium-base alloy, zirconium-base alloy includes that Zr-Sn system, Zr-Nb system or Zr-Sn-Nb system close
Gold.
3. the preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube as claimed in claim 1, wherein in step b
Described 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 claimed in claim 1, wherein in step c
Front zircaloy pipe and titanium alloy pipe are machined out and surface clean, make contact surface keep cleaning.
5. the preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube as claimed in claim 1, wherein in step c
It is evacuated to less than 3 × 10-3Pa。
6. the preparation method of Reactor fuel element cladding zircaloy titanium alloy composite tube as claimed in claim 1, wherein in step d
Heating-up temperature be 700 DEG C-1250 DEG C.
7. a Reactor fuel element cladding zircaloy titanium alloy composite tube, it is characterised in that described multiple tube includes metallurgical binding
Internal layer tubing and outer layer tubing, described internal layer tubing is zircaloy, and described outer layer tubing is titanium alloy, and described multiple tube also wraps
Include the metallurgical bonding layer between described internal layer tubing and described outer layer tubing, the element that described metallurgical bonding layer contains from
Described internal layer tubing and described outer layer tubing.
8. Reactor fuel element cladding zircaloy stainless steel composite pipe as claimed in claim 7, wherein said metallurgical bonding layer contains
Some elements include the one 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 multiple.
9. Reactor fuel element cladding zircaloy titanium alloy composite tube as claimed in claim 7, the thickness of wherein said internal layer tubing
Degree is 0.05mm～0.95mm, and the thickness of described outer layer tubing is 0.05mm～0.70mm, and the thickness of described metallurgical bonding layer is
0.001mm～0.20mm.
10. a nuclear fuel rod for use Reactor fuel element cladding zircaloy titanium alloy composite tube as described in claim 7-9,
It is characterized in that, described nuclear fuel rod includes fuel core body and involucrum.Described involucrum is zircaloy titanium alloy composite tube, from interior to
Being followed successively by outward zircaloy, metallurgical bonding layer and titanium alloy, described fuel core body is arranged in described zircaloy titanium alloy composite tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| 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 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| 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 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106128532A true CN106128532A (en) | 2016-11-16 |
| CN106128532B CN106128532B (en) | 2018-10-12 |
Family
ID=57270929
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610417182.1A Active CN106128532B (en) | 2016-06-12 | 2016-06-12 | A kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and preparation method thereof |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106128532B (en) |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107116339A (en) * | 2017-05-03 | 2017-09-01 | 中国核动力研究设计院 | A kind of zirconium alloy cladding tubing preparation technology |
| 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 |
| CN108231214A (en) * | 2017-12-07 | 2018-06-29 | 广东核电合营有限公司 | Nuclear fuel assembly multiple tube and its manufacturing method |
| CN110871327A (en) * | 2018-09-03 | 2020-03-10 | 核工业西南物理研究院 | Fusion reactor high-heat-load multilayer composite pipe and manufacturing method thereof |
| CN110914919A (en) * | 2017-07-19 | 2020-03-24 | 泰拉能源公司 | Nuclear fuel element resistant to chemical interaction of fuel cladding and method for manufacturing same |
| CN111344807A (en) * | 2017-11-14 | 2020-06-26 | 韩国原子力研究院 | Zirconium alloy cladding tube with improved high-temperature oxidation resistance and preparation method thereof |
| CN113424272A (en) * | 2018-11-20 | 2021-09-21 | 西屋电气有限责任公司 | Coating and surface modification to reduce SiC cladding loss during light water reactor operation |
| 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 |
| CN114261153A (en) * | 2021-10-18 | 2022-04-01 | 贵州盛航云集科技有限公司 | Metal or alloy composite structure and preparation method and application 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 |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5225154A (en) * | 1988-08-02 | 1993-07-06 | Hitachi, Ltd. | Fuel assembly for nuclear reactor, method for producing the same and structural members for the same |
| JPH0727884A (en) * | 1993-07-14 | 1995-01-31 | Kobe Steel Ltd | Nuclear reactor clad fuel tube superior in corrosion resistance and its production method |
| CN1375362A (en) * | 2002-04-11 | 2002-10-23 | 中国石化集团洛阳石油化工工程公司 | Manufacture of bimetallic composite pipe |
| CN101031355A (en) * | 2004-08-02 | 2007-09-05 | Ati资产公司 | Methods for replacing corroded fluid conducting parts in equipment via welding, and parts obtained thereby |
| KR20130117124A (en) * | 2012-04-17 | 2013-10-25 | 충남대학교산학협력단 | Zirconium-ceramic hybrid tube for nuclear fuel rod cladding and method for manufacturing the same |
| CN103846305A (en) * | 2012-12-07 | 2014-06-11 | 北京有色金属研究总院 | Preparation machining method of large-diameter pipe material and special-shaped pipe fitting |
-
2016
- 2016-06-12 CN CN201610417182.1A patent/CN106128532B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5225154A (en) * | 1988-08-02 | 1993-07-06 | Hitachi, Ltd. | Fuel assembly for nuclear reactor, method for producing the same and structural members for the same |
| JPH0727884A (en) * | 1993-07-14 | 1995-01-31 | Kobe Steel Ltd | Nuclear reactor clad fuel tube superior in corrosion resistance and its production method |
| CN1375362A (en) * | 2002-04-11 | 2002-10-23 | 中国石化集团洛阳石油化工工程公司 | Manufacture of bimetallic composite pipe |
| CN101031355A (en) * | 2004-08-02 | 2007-09-05 | Ati资产公司 | Methods for replacing corroded fluid conducting parts in equipment via welding, and parts obtained thereby |
| KR20130117124A (en) * | 2012-04-17 | 2013-10-25 | 충남대학교산학협력단 | Zirconium-ceramic hybrid tube for nuclear fuel rod cladding and method for manufacturing the same |
| CN103846305A (en) * | 2012-12-07 | 2014-06-11 | 北京有色金属研究总院 | Preparation machining method of large-diameter pipe material and special-shaped pipe fitting |
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107116339A (en) * | 2017-05-03 | 2017-09-01 | 中国核动力研究设计院 | A kind of zirconium alloy cladding tubing preparation technology |
| CN110914919A (en) * | 2017-07-19 | 2020-03-24 | 泰拉能源公司 | Nuclear fuel element resistant to chemical interaction of fuel cladding and method for manufacturing 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 |
| CN111344807A (en) * | 2017-11-14 | 2020-06-26 | 韩国原子力研究院 | Zirconium alloy cladding tube with improved high-temperature oxidation resistance and preparation method thereof |
| CN108231214A (en) * | 2017-12-07 | 2018-06-29 | 广东核电合营有限公司 | Nuclear fuel assembly multiple tube and its manufacturing method |
| CN110871327A (en) * | 2018-09-03 | 2020-03-10 | 核工业西南物理研究院 | Fusion reactor high-heat-load multilayer composite pipe and manufacturing method thereof |
| 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 |
| CN113424272A (en) * | 2018-11-20 | 2021-09-21 | 西屋电气有限责任公司 | Coating and surface modification to reduce SiC cladding loss during light water reactor operation |
| CN114261153A (en) * | 2021-10-18 | 2022-04-01 | 贵州盛航云集科技有限公司 | Metal or alloy composite structure and preparation method and application thereof |
| 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106128532B (en) | 2018-10-12 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106128532B (en) | A kind of Reactor fuel element cladding zircaloy titanium alloy composite tube and preparation method thereof | |
| CN106078086A (en) | A kind of Reactor fuel element cladding zircaloy stainless steel composite pipe and preparation method thereof | |
| JP4018169B2 (en) | Method of manufacturing tube for nuclear fuel assembly and tube obtained thereby | |
| EP0155168B1 (en) | Composite nuclear fuel element cladding tube | |
| EP1111623B1 (en) | Zirconium niobium tin alloys for nuclear fuel rods and structural parts for high burnup | |
| US4938921A (en) | Method of manufacturing a zirconium-based alloy tube for a nuclear fuel element sheath and tube thereof | |
| EP0155167B1 (en) | Cladding tubes for containing nuclear fuel material | |
| JPH01267493A (en) | Fuel element having acid resisting cover | |
| KR970004349B1 (en) | Fuel rod for a nuclear reactor fuel assembly | |
| KR20060123781A (en) | Zirconium alloys with improved corrosion resistance and method for fabricating zirconium alloys with improved corrosion resistance | |
| CN103409661B (en) | For the zirconium-niobium alloy of reactor nuclear fuel assembly | |
| JPS6239787A (en) | Composite nuclear fuel coated tube | |
| EP0908897B1 (en) | Zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup | |
| US4613479A (en) | Water reactor fuel cladding | |
| EP0899747A2 (en) | Method of manufacturing zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup | |
| JPH0529080B2 (en) | ||
| JP4982654B2 (en) | Zirconium alloy with improved corrosion resistance and method for producing zirconium alloy with improved corrosion resistance | |
| JPH0528357B2 (en) | ||
| CN103194718B (en) | High-temperature corrosion resisting zirconium alloy tube and laser surface pre-oxidation method of zirconium alloy tube | |
| EP0194797B1 (en) | Water reactor fuel element cladding tube | |
| JPH07173587A (en) | Production of zirconium alloy welded member | |
| JPH11118968A (en) | Composite cladding tube for nuclear fuel | |
| JPH0812259B2 (en) | Nuclear fuel element | |
| JPS61150788A (en) | Joining method of zirconium alloy and hafnium | |
| JPS618695A (en) | Nuclear fuel element |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| TR01 | Transfer of patent right | ||
| TR01 | Transfer of patent right |
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 |
|
| 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. |