CN106078086A - A kind of Reactor fuel element cladding zircaloy stainless steel composite pipe and preparation method thereof - Google Patents
A kind of Reactor fuel element cladding zircaloy stainless steel composite pipe and preparation method thereof Download PDFInfo
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- CN106078086A CN106078086A CN201610411172.7A CN201610411172A CN106078086A CN 106078086 A CN106078086 A CN 106078086A CN 201610411172 A CN201610411172 A CN 201610411172A CN 106078086 A CN106078086 A CN 106078086A
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- zircaloy
- pipe
- stainless steel
- composite pipe
- steel composite
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23P—METAL-WORKING NOT OTHERWISE PROVIDED FOR; COMBINED OPERATIONS; UNIVERSAL MACHINE TOOLS
- B23P15/00—Making specific metal objects by operations not covered by a single other subclass or a group in this subclass
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- 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
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- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Pressure Welding/Diffusion-Bonding (AREA)
Abstract
The invention discloses a kind of Reactor fuel element cladding zircaloy stainless steel composite pipe 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 rustless steel, is metallurgical bonding layer between zirconium alloy tube and stainless steel 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 stainless steel composite pipe 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 decay resistance 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 stainless steel composite pipe 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 stainless steel composite pipe, comprises the following steps:
A) by zircaloy blank through processing, it is prepared as zircaloy pipe；
B) by rustless steel blank through processing, it is prepared as Stainless pipe billet；
C) Stainless pipe billet is assemblied in outside zircaloy pipe, puts into electron beam weldering case evacuation, then to rustless steel
Pipe and the upper surface of zircaloy pipe and lower surface carry out electron beam welding, make Stainless pipe billet 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 not by rolling mill practice
Rust steel pipe, has metallurgical bonding layer between zirconium alloy pipe and stainless steel tube in zircaloy stainless steel composite pipe.
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 rustless steel blank in step b is ferritic stainless steel, austenitic stainless steel or oxide dispersion intensifying
(ODS) steel.
Preferably, before step c, zircaloy pipe and Stainless pipe billet 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 stainless steel composite pipe, 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 rustless steel, 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, Fe, Cr, Mn, Sn, Ni, Al, Mo, Co, Nb, Ti, V, Cu,
One or more in the element such as W, O, Si, B, C, N, P, S, Be, Se and rare earth.
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 stainless steel composite pipe, nuclear fuel rod includes cartridge
Body and involucrum.Involucrum is zircaloy stainless steel composite pipe, is followed successively by zircaloy, metallurgical bonding layer and rustless steel from inside to outside, combustion
Material core body is arranged in zircaloy stainless steel composite pipe.
Due to the employing of technique scheme, the present invention has the following characteristics that compared with zirconium alloy cladding tubing
First, the zircaloy stainless steel composite pipe 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 stainless steel layer, closes owing to stainless steel 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 stainless steel dissimilar metal composite pipe, is metallurgical bonding layer between zirconium alloy tube and stainless steel pipe.This smelting
Gold binder course plays cementation, makes to combine closely between zircaloy and rustless steel very close to each other, owing to stainless high temperature is strong
Degree 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 stainless steel 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 stainless steel dissimilar metal composite pipe 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 rustless steel.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；Rustless steel is preferably 0Cr18Ni9Ti rustless steel, and stainless steel pipe thickness is 0.15-0.35mm；Metallurgical binding thickness
Degree is 0.01mm-0.1mm.The thickness of zircaloy stainless steel composite pipe is 0.50mm-0.65mm, and external diameter is 8.0mm-12mm, long
Degree is 1.0m-6.0m.
Preparation process and the step of the zircaloy stainless steel dissimilar metal composite pipe 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, 0Cr18Ni9Ti rustless steel blank is prepared as 0Cr18Ni9Ti Stainless pipe billet；
(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, Stainless pipe billet (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 stainless steel tube (outer layer tubing 2).
Owing to the 0Cr18Ni9Ti rustless steel 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,
The stainless elevated temperature strength of 0Cr18Ni9Ti is better than zircaloy, and therefore, the heat resistance of this multiple tube is better than zircaloy.Cause
This, compared with zirconium alloy cladding pipe, the dissimilar metal multiple tube of the present invention has the most excellent water-fast side corrosive nature and relatively
High heat resistance, can improve the ability of the anti-LOCA accident of fuel rod, it is adaptable under nuclear reactor relatively high burnup or higher temperature
Under fuel rod clad pipe.
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 stainless steel composite pipe, it is characterised in that comprise the following steps:
A) by zircaloy blank through processing, it is prepared as zircaloy pipe；
B) by rustless steel blank through processing, it is prepared as Stainless pipe billet；
C) Stainless pipe billet is assemblied in outside zircaloy pipe, puts into electron beam weldering case evacuation, then to Stainless pipe billet
Carry out electron beam welding with upper surface and the lower surface of zircaloy pipe, make Stainless pipe billet 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 rustless steel by rolling mill practice
Multiple tube, has metallurgical bonding layer between zirconium alloy pipe and stainless steel tube in zircaloy stainless steel composite pipe.
2. the preparation method of Reactor fuel element cladding zircaloy stainless steel composite pipe 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 stainless steel composite pipe as claimed in claim 1, wherein in step b
Described rustless steel blank be ferritic stainless steel, austenitic stainless steel or oxide dispersion intensifying steel.
4. the preparation method of Reactor fuel element cladding zircaloy stainless steel composite pipe as claimed in claim 1, wherein in step c
Front zircaloy pipe and Stainless pipe billet are machined out and surface clean, make contact surface keep cleaning.
5. the preparation method of Reactor fuel element cladding zircaloy stainless steel composite pipe 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 stainless steel composite pipe 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 stainless steel composite pipe, 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 rustless steel, 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 Zr, Fe, Cr, Mn, Sn, Ni, Al, Mo, Co, Nb, Ti, V, Cu, W, O, Si, B, C, N, P, S, Be, Se and dilute
One or more in the elements such as soil.
9. Reactor fuel element cladding zircaloy stainless steel composite pipe 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 stainless steel composite pipe 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 stainless steel composite pipe, from interior to
Being followed successively by outward zircaloy, metallurgical bonding layer and rustless steel, described fuel core body is arranged in described zircaloy stainless steel composite pipe.
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| CN201610411172.7A CN106078086B (en) | 2016-06-12 | 2016-06-12 | Zirconium alloy stainless steel composite tube for nuclear fuel element cladding and preparation method thereof |
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| CN106475436A (en) * | 2016-11-15 | 2017-03-08 | 江松伟 | A kind of processing method of metal pipe material |
| CN109972048A (en) * | 2018-05-25 | 2019-07-05 | 中国科学院金属研究所 | Nuclear reactor used by nuclear fuel jacketing FeCrAl alloy and the heat-resisting steel pipe of T91 ferrite/martensite and preparation |
| CN109994223A (en) * | 2017-12-29 | 2019-07-09 | 中国核动力研究设计院 | A kind of novel dispersion fuel and its manufacturing method |
| JP2019527296A (en) * | 2016-07-01 | 2019-09-26 | サンドビック インテレクチュアル プロパティー アクティエボラーグ | Bimetal pipe and method for producing bimetal pipe |
| CN110379525A (en) * | 2019-08-02 | 2019-10-25 | 上海核工程研究设计院有限公司 | A kind of rodlike nuclear fuel element of crash-proof and preparation method thereof |
| CN110415838A (en) * | 2019-08-02 | 2019-11-05 | 上海核工程研究设计院有限公司 | A kind of rodlike nuclear fuel element and preparation method thereof enhancing safety |
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| JP2019527296A (en) * | 2016-07-01 | 2019-09-26 | サンドビック インテレクチュアル プロパティー アクティエボラーグ | Bimetal pipe and method for producing bimetal pipe |
| CN106475436A (en) * | 2016-11-15 | 2017-03-08 | 江松伟 | A kind of processing method of metal pipe material |
| CN109994223A (en) * | 2017-12-29 | 2019-07-09 | 中国核动力研究设计院 | A kind of novel dispersion fuel and its manufacturing method |
| CN109972048A (en) * | 2018-05-25 | 2019-07-05 | 中国科学院金属研究所 | Nuclear reactor used by nuclear fuel jacketing FeCrAl alloy and the heat-resisting steel pipe of T91 ferrite/martensite and preparation |
| CN109972048B (en) * | 2018-05-25 | 2021-03-26 | 中国科学院金属研究所 | FeCrAl alloy and ferrite/martensite heat-resistant steel composite tube for nuclear fuel cladding of nuclear reactor and preparation method thereof |
| CN110379525A (en) * | 2019-08-02 | 2019-10-25 | 上海核工程研究设计院有限公司 | A kind of rodlike nuclear fuel element of crash-proof and preparation method thereof |
| CN110415838A (en) * | 2019-08-02 | 2019-11-05 | 上海核工程研究设计院有限公司 | A kind of rodlike nuclear fuel element and preparation method thereof enhancing safety |
| CN110379525B (en) * | 2019-08-02 | 2022-05-10 | 上海核工程研究设计院有限公司 | Rod-shaped nuclear fuel element resistant to accidents and preparation method thereof |
| CN110415838B (en) * | 2019-08-02 | 2022-07-22 | 上海核工程研究设计院有限公司 | Rod-shaped nuclear fuel element with enhanced safety and preparation method thereof |
| CN114121307A (en) * | 2021-11-23 | 2022-03-01 | 中国核动力研究设计院 | Composite cladding tube with internal buffer layer and fuel rod formed by composite cladding tube |
| CN115781179A (en) * | 2022-12-21 | 2023-03-14 | 中国核动力研究设计院 | Rod-shaped nuclear fuel element magnetic pulse close fit packaging-connection cooperative forming device and method |
| CN115781179B (en) * | 2022-12-21 | 2024-06-11 | 中国核动力研究设计院 | Magnetic pulse close fitting packaging-connecting collaborative forming device and method for rod type nuclear fuel element |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: Shanghai Nuclear Engineering Research & Design Institute |
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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. |