CN102230109B - Zirconium alloy material for nuclear reactor - Google Patents
Zirconium alloy material for nuclear reactor Download PDFInfo
- Publication number
- CN102230109B CN102230109B CN2011101801022A CN201110180102A CN102230109B CN 102230109 B CN102230109 B CN 102230109B CN 2011101801022 A CN2011101801022 A CN 2011101801022A CN 201110180102 A CN201110180102 A CN 201110180102A CN 102230109 B CN102230109 B CN 102230109B
- Authority
- CN
- China
- Prior art keywords
- alloy
- zirconium
- alloy material
- nuclear reactor
- percent
- 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.)
- Active
Links
Classifications
-
- 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
- Turbine Rotor Nozzle Sealing (AREA)
- Manufacture And Refinement Of Metals (AREA)
Abstract
The invention discloses a zirconium alloy material for a nuclear reactor, which consists of the following components in percentage by weight on the basis of the total weight of the alloy material: 0.9 to 1.2 percent of Nb, 0.45 to 0.55 percent of Sn, 0.01 to 0.1 percent of Cu, 0.05 to 0.15 percent of Ni, 0.05 to 0.15 percent of Cr, 600 to 1,400 ppm of O, less than or equal to 100 ppm of C, less than or equal to 80 ppm of N and the balance of Zr. A series of experimental data indicate that compared with the conventional low-stannum Zr-4 alloy, the zirconium alloy material has the high corrosion resistance in high-temperature steam of 427 DEG C and meets the application requirement of a nuclear reactor material.
Description
Technical field
The present invention relates to the Zirconium alloy material field, especially relate to a kind of energy as the corrosion-resistant Zirconium alloy material of the fuel rod clad material in light-water nuclear power plant nuclear reactor.
Background technology
The thermal neutron absorption cross section of zirconium is very little, and has good high-temperature resistant water corrosive nature and mechanical property, and therefore zirconium base alloy is widely used as the can material of fuel stick and the structural element of nuclear reactor core in water cooled nuclear reactor., towards the future development that improves fuel burnup and reduction fuel cycle cost, raising reactor thermo-efficiency, raising safe reliability the performances such as corrosion resistance, hydrogen sucking function, mechanical property and irradiation dimensional stability of key core parts fuel element can material zirconium base alloy are had higher requirement along with the power producer technology.Creep and fatigue under condition (irradiation, high temperature, high pressure and complicated stress), occur in fuel element under arms.Creep property is one of the major issue that will consider when working in the water-cooled power reactor of zirconium base alloy, a large amount of research has been carried out in the creep of zirconium base alloy both at home and abroad.Early development goes out in the sixties in last century zirconium base alloy such as Zr-4 alloy, it has excellent physical strength, creep resistance, heat conductivity and low neutron-absorption cross-section under the reactor working temperature, and uses so far widely.the burnup design load of the fuel for nuclear power plant that the Zr-4 alloy that is due to conventional Zr-Sn can satisfy is generally 33GWd/tU, therefore, in order to satisfy the requirement of high burnup and long lifetime reactor core, on the one hand, many countries have all carried out the corrosion research that improves the Zr-4 alloy since 20 century 70s, research can better new type zirconium-based alloy on the other hand, the exploitation of new type zirconium-based alloy tends to reduce or eliminate the content of tin (Sn), wherein the most outstanding achievement is to have developed low tin Zr-4 alloy, or be referred to as to optimize the Zr-4 alloy, design burn-up can reach 45GWd/tU.
Chinese invention patent application 200810084446.1 discloses the zirconium base alloy that is used for nuclear reactor, and wherein disclose a kind of alloy component as follows: Sn 0.65%～1.2%; Nb 0.2%～0.45%, Fe 0.2%～0.4%, Cr 0.01%～0.2%, O 0.06%～0.15%, V 0.002%～0.2%, and C 0.012～0.015%, and N 0.006%～0.008% and surplus are Zr.This zirconium base alloy has good anti-all even Nodular Corrosions, has higher creep resistance and fatigability, has anti-irradiation growth performance.Although it is above-mentioned that this alloy has advantages of, tin content is still higher.
Summary of the invention
Technical problem to be solved by this invention is to overcome the deficiencies in the prior art, provides a kind of tin content lower used by nuclear reactor Zirconium alloy material, and it has good erosion resistance and good mechanical property.
For solving above technical problem, the present invention adopts following technical scheme:
A kind of used by nuclear reactor Zirconium alloy material, take the gross weight of described zirconium-based alloy material as benchmark, it is comprised of following component: Nb 0.9%～1.1%, Sn 0.45%～0.55%, Cu 0.01%～0.1%, Ni0.05%～0.15%, Cr 0.05%～0.15%, O 600～1400ppm, C≤100ppm, N≤80ppm and Zr surplus.
Preferably, in above-mentioned alloy material, Ni is 0.9～1.1: 1 with the ratio of the content of Cr.
An exemplary alloy formula according to the present invention is: Nb 1%, Sn 0.5%, Cu 0.05%, Ni0.1%, Cr 0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm and Zr surplus.
In above-mentioned alloy formula, C and the N inevitable impurity for bringing from raw material, one of ordinary skill in the art should be understood, other inevitable impurity component that some that may also comprise in above-mentioned alloy formula are brought from raw material can not cause disadvantageous effect to zirconium base alloy of the present invention when these impurity components exist with inevitable amount.
The present invention compared with prior art has the following advantages: the present invention is optimized design to existing zirconium alloy formula, makes at Sn content hour, still has excellent erosion resistance and good mechanical property.
Embodiment
The present invention will be further described below in conjunction with specific embodiment, but the invention is not restricted to following examples:
Prepare burden by mass percentage with the form of master alloy and adopt vacuum arc fumace to carry out repeatedly melting and make alloy pig with core level zirconium sponge (Zr content is greater than 97%), Cr, Ni, Cu, Nb and Sn element; Chemical composition analysis is carried out in sampling to ingot casting, and alloying constituent sees Table 1.Ingot casting makes the zirconium base alloy sheet material of corresponding composition through operations such as forging, hot rolling, cold rolling, annealing.
Eight kinds of zirconium base alloy sheet material and the low tin Zr-4 alloy of Comparative Examples to embodiments of the invention 1-8 carry out the corrosive nature test.Corrosion test is carried out in autoclave, and etching condition is 400 ℃/10.3MPa superheated vapour and 427 ℃/10.3MPa superheated vapour.Table 1 has provided according to embodiments of the invention 1-8 and the composition proportion of the zirconium base alloy of the low tin Zr-4 alloy of Comparative Examples and erosion rate and the relative erosion rate under their each comfortable above-mentioned etching conditions.
The zirconium alloy of table 1 embodiment 1-8 forms and corrosion resistance nature
Can find out from the data of table 1, zirconium alloy of the present invention in 427 ℃ of steam erosion rate lower than 1.10mg/ (dm
2* d), erosion rate is less than 0.80mg/ (dm in 400 ℃ of steam
2* d), with low tin Zr-4 alloy phase ratio, its corrosion resistance at high temperature is more excellent.In addition, zirconium alloy of the present invention has also shown the excellent mechanical properties such as welding characteristic, satisfies the power station to the requirement of can material corrosive nature.
Above-described embodiment only is explanation technical conceive of the present invention and characteristics, and its purpose is to allow person skilled in the art scholar can understand content of the present invention and implement according to this, can not limit protection scope of the present invention with this.All equivalences that spirit is done according to the present invention change or modify, within all should being encompassed in protection scope of the present invention.
Claims (1)
1. used by nuclear reactor Zirconium alloy material, it is characterized in that: take the gross weight of described zirconium-based alloy material as benchmark, described zirconium-based alloy material is comprised of following component: Nb 1.0%, Sn 0.5%, Cu 0.05%, Ni 0.1%, Cr 0.1%, O 980ppm, C≤100ppm, N≤80ppm and Zr surplus.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2011101801022A CN102230109B (en) | 2011-06-30 | 2011-06-30 | Zirconium alloy material for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2011101801022A CN102230109B (en) | 2011-06-30 | 2011-06-30 | Zirconium alloy material for nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN102230109A CN102230109A (en) | 2011-11-02 |
| CN102230109B true CN102230109B (en) | 2013-06-12 |
Family
ID=44842712
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2011101801022A Active CN102230109B (en) | 2011-06-30 | 2011-06-30 | Zirconium alloy material for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102230109B (en) |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5211774A (en) * | 1991-09-18 | 1993-05-18 | Combustion Engineering, Inc. | Zirconium alloy with superior ductility |
| CN1818111A (en) * | 2005-02-07 | 2006-08-16 | 韩国原子力研究所 | Zirconium based alloys having excellent creep resistance |
| CN101270426A (en) * | 2008-03-24 | 2008-09-24 | 中国核动力研究设计院 | Zirconium based alloy for nuclear reactor |
-
2011
- 2011-06-30 CN CN2011101801022A patent/CN102230109B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5211774A (en) * | 1991-09-18 | 1993-05-18 | Combustion Engineering, Inc. | Zirconium alloy with superior ductility |
| CN1818111A (en) * | 2005-02-07 | 2006-08-16 | 韩国原子力研究所 | Zirconium based alloys having excellent creep resistance |
| CN101270426A (en) * | 2008-03-24 | 2008-09-24 | 中国核动力研究设计院 | Zirconium based alloy for nuclear reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| CN102230109A (en) | 2011-11-02 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN102251150A (en) | Zirconium alloy for nuclear reactor | |
| CN101654751B (en) | Niobium-containing zirconium base alloy used by nuclear fuel jacketing | |
| CN102212718B (en) | Low tin-zirconium alloy material for nuclear reactor fuel assembly | |
| CN102181749B (en) | Zirconium alloy for nuclear pressurized water reactor and preparation method thereof | |
| CN102864338B (en) | Corrosion resistant zirconium-based alloy used for high burnup and preparation method thereof | |
| CN105483442B (en) | Nuclear reactor fuel can zirconium-niobium alloy and preparation method thereof | |
| CN101413073B (en) | Magnesium-containing zirconium-niobium alloy for nuclear reactor fuel can | |
| CN102220520B (en) | Zirconium alloy for fuel cladding of nuclear reactor | |
| CN103898368A (en) | Zirconium-based alloy for nuclear fuel assembly | |
| CN103589910B (en) | The zirconium ferrocolumbium of sulfur-bearing for fuel for nuclear power plant involucrum | |
| CN102220519B (en) | Zirconium alloy used as structural material of nuclear pressurized water reactor | |
| CN101413074A (en) | Zirconium based alloy for nuclear reactor | |
| CN102251149A (en) | Zirconium-tin-niobium zirconium alloy for can material of nuclear reactor | |
| CN102251148B (en) | Zirconium alloy for nuclear reactor | |
| CN102230109B (en) | Zirconium alloy material for nuclear reactor | |
| CN102212719B (en) | Low-tin-zirconium alloy material for nuclear reactor | |
| CN101649404B (en) | Corrosion-resistant Zr-based alloy for cladding nuclear fuels | |
| CN102220521B (en) | Zirconium alloy for nuclear reactor | |
| CN102220518B (en) | Low tin-zirconium alloy for nuclear reactor canning material | |
| CN102140595B (en) | Zirconium alloy for canning nuclear fuel | |
| CN102268572A (en) | Low tin zirconium-based alloy for nuclear reactor cladding material | |
| CN105018794A (en) | Zirconium/niobium/copper/bismuth alloy for fuel cladding of nuclear power plant | |
| CN102268571A (en) | Zirconium alloy material | |
| CN102925750B (en) | The germanic zirconium-niobium alloy of fuel for nuclear power plant involucrum | |
| CN102251151A (en) | Zirconium alloy material applied to nuclear reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C56 | Change in the name or address of the patentee | ||
| CP01 | Change in the name or title of a patent holder |
Address after: 215004 West Ring Road, Jiangsu, Suzhou, No. 1788 Patentee after: Suzhou Nuclear Power Research Institute Co., Ltd. Patentee after: China General Nuclear Power Corporation Address before: 215004 West Ring Road, Jiangsu, Suzhou, No. 1788 Patentee before: Suzhou Nuclear Power Research Institute Co., Ltd. Patentee before: China Guangdong Nuclear Power Group Co., Ltd. |