CN106078086B - Zirconium alloy stainless steel composite tube for nuclear fuel element cladding and preparation method thereof - Google Patents
Zirconium alloy stainless steel composite tube for nuclear fuel element cladding and preparation method thereof Download PDFInfo
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- CN106078086B CN106078086B CN201610411172.7A CN201610411172A CN106078086B CN 106078086 B CN106078086 B CN 106078086B CN 201610411172 A CN201610411172 A CN 201610411172A CN 106078086 B CN106078086 B CN 106078086B
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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
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- 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
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- 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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Abstract
The invention discloses a zirconium alloy stainless steel composite tube for a nuclear fuel element cladding and a preparation method thereof. The composite pipe comprises an inner layer pipe and an outer layer pipe which are metallurgically bonded, wherein the inner layer pipe is zirconium alloy, the outer layer pipe is stainless steel, and a metallurgically bonded layer is arranged between the zirconium alloy pipe and the stainless steel pipe. The metallurgical bonding layer contains elements from the inner and outer pipe. Compared with a zirconium alloy cladding tube, the zirconium alloy stainless steel composite tube is a dissimilar metal composite tube, has more excellent water side corrosion resistance and better heat strength, can improve the LOCA accident resistance of the fuel rod, and is suitable for the fuel rod cladding tube under higher fuel consumption or higher temperature of a water-cooled nuclear reactor.
Description
Technical Field
The invention relates to the field of nuclear fuel element cladding, in particular to a fuel rod cladding tube which can be used for a water-cooled nuclear reactor under higher fuel consumption or higher temperature. In particular, the present invention relates to fuel cladding tubes exhibiting improved corrosion resistance and better thermal strength in water-cooled nuclear reactors, which cladding tubes improve the fuel rod's ability to withstand a LOCA accident.
Background
The zirconium alloy has small thermal neutron absorption cross section, high thermal conductivity, good mechanical property, good processing property and the same UO2Good compatibility, especially good for high temperature water and high temperature steamCorrosion resistance and sufficient heat strength, and thus are widely used as a cladding material and a core structural material of a water-cooled power reactor.
Currently, although the alloy elements that can be added to zirconium alloys are limited by the size of the thermal neutron absorption cross section, various series of zirconium alloys are formed, and the three main types of zirconium alloys, including Zr — Sn, Zr — Nb, and Zr — Sn — Nb, are summarized. The Zr-Sn system mainly includes Zr-2 alloy, Zr-4 alloy, low-tin Zr-4 alloy, etc., the Zr-Nb system includes Zr-2.5% Nb alloy (all components are in mass percentages herein unless otherwise specified), Zr-1% Nb alloy and M5 alloy, and the Zr-Sn-Nb system includes ZIRLO alloy of West House company, NDA alloy of Japan, E635 alloy of Russia, and N18 alloy, N36 alloy of China, etc.
In order to further improve the economy and safety of nuclear power, nuclear fuel elements are developed in the direction of high fuel consumption and long circulation, which continuously provides new requirements and challenges for zirconium alloy cladding materials. For this reason, the development of zirconium alloy research has never been stopped in countries around the world.
The burning-up rate of the first-generation zirconium alloy such as the conventional Zr-4 alloy can only reach 30Gwd/tU, and the burning-up rate of the optimized Zr-4 alloy can reach 40-50 Gwd/tU;
the second generation zirconium alloy was developed at home and abroad since the last 70 s, and the main applications of the second generation zirconium alloy in pressurized water reactors are as follows: e635 alloy, ZIRLO alloy, M5 alloy, and the like. The combustion consumption of the ZIRLO alloy approved fuel assembly is 60Gwd/tU, and the combustion consumption of the optimized ZIRLO alloy approved fuel assembly can reach 70 Gwd/tU; the M5 alloy was approved for fuel assembly burnup of 52-62Gwd/tU, and the Germany approved M5 alloy fuel assembly burnup reached 70 Gwd/tU.
At present, new zirconium alloy cladding materials are continuously developed at home and abroad to improve the corrosion resistance, hydrogen absorption performance, mechanical property, irradiation growth resistance and irradiation creep resistance of the zirconium alloy cladding materials, wherein the corrosion resistance and the hydrogen absorption performance are the most critical and most easily changed performances of the zirconium alloy.
After the nuclear accident of fukushima in 2011 of japan, higher requirements are made on the capability of a fuel rod to resist the LOCA accident. Currently, those skilled in the art have attempted to find a fuel rod cladding material that is resistant to the LOCA accident.
Disclosure of Invention
In view of the defects of the existing zirconium alloy cladding tube, the technical problem to be solved by the invention is to provide a novel fuel rod cladding tube which is resistant to corrosion of high-temperature and high-pressure water media, has more excellent corrosion resistance and better heat strength, and can improve the LOCA accident resistance of a fuel rod.
In order to achieve the aim, the invention provides a zirconium alloy stainless steel composite tube for a nuclear fuel element cladding and a preparation method thereof, and specifically provides the following technical scheme:
a preparation method of a zirconium alloy stainless steel composite tube for a nuclear fuel element cladding comprises the following steps:
a) processing the zirconium alloy blank to prepare a zirconium alloy tube blank;
b) processing the stainless steel blank to prepare a stainless steel pipe blank;
c) assembling a stainless steel pipe blank outside a zirconium alloy pipe blank, putting the stainless steel pipe blank into an electron beam welding box for vacuumizing, and then carrying out electron beam welding on the upper end surface and the lower end surface of the stainless steel pipe blank and the zirconium alloy pipe blank to keep a gap between contact surfaces of the stainless steel pipe blank and the zirconium alloy pipe blank vacuum so as to obtain an extruded pipe blank;
d) wrapping the extruded tube blank with an inner sheath and an outer sheath, heating under a vacuum condition or under the protection of inert gas, and then extruding by using an extruder to obtain a rolled tube blank;
e) and removing the inner sheath and the outer sheath, cleaning the rolled tube blank, and then obtaining the zirconium alloy stainless steel composite tube through a rolling process, wherein a metallurgical bonding layer is arranged between the zirconium alloy tube and the stainless steel tube in the zirconium alloy stainless steel composite tube.
Preferably, the zirconium alloy ingot in step a comprises pure zirconium and a zirconium based alloy, the zirconium based alloy comprising a Zr-Sn, Zr-Nb or Zr-Sn-Nb based alloy.
Preferably, the stainless steel blank in step b is a ferritic stainless steel, an austenitic stainless steel, or an Oxide Dispersion Strengthened (ODS) steel.
Preferably, the zirconium alloy tube blank and the stainless steel tube blank are machined and surface cleaned before step c to keep the contact surfaces clean.
Preferably, step c is performed by applying a vacuum of less than 3X 10-3Pa。
Preferably, the heating temperature in step d is from 700 ℃ to 1250 ℃.
The composite tube comprises an inner layer tube and an outer layer tube which are metallurgically bonded, wherein the inner layer tube is made of zirconium alloy, the outer layer tube is made of stainless steel, the composite tube further comprises a metallurgically bonded layer positioned between the inner layer tube and the outer layer tube, and elements contained in the metallurgically bonded layer come from the inner layer tube and the outer layer tube.
Preferably, the metallurgical bonding layer comprises elements including one or more of Zr, Fe, Cr, Mn, Sn, Ni, Al, Mo, Co, Nb, Ti, V, Cu, W, O, Si, B, C, N, P, S, Be, Se and rare earths.
Preferably, the thickness of the inner layer pipe is 0.05 mm-0.95 mm, the thickness of the outer layer pipe is 0.05 mm-0.70 mm, and the thickness of the metallurgical bonding layer is 0.001 mm-0.20 mm.
A nuclear fuel rod using a nuclear fuel element clad zirconium alloy stainless steel composite tube includes a fuel core and a cladding. The cladding is a zirconium alloy stainless steel composite pipe, the zirconium alloy, the metallurgical bonding layer and the stainless steel are sequentially arranged from inside to outside, and the fuel core is arranged in the zirconium alloy stainless steel composite pipe.
Due to the adoption of the technical scheme, compared with the zirconium alloy clad pipe, the invention has the following characteristics:
firstly, the zirconium alloy stainless steel composite pipe obtained by the invention is a dissimilar metal composite pipe, and the water side corrosion resistance of the zirconium alloy stainless steel composite pipe is superior to that of a zirconium alloy cladding pipe. The stainless steel layer is added on the outer side of the nuclear fuel cladding zirconium alloy tube in the prior art through metallurgical bonding, and the corrosion resistance of the stainless steel material in a high-temperature and high-pressure water medium is superior to that of zirconium alloy, so that the stainless steel tube has a low oxidation rate particularly under a steam condition, and embrittlement failure of the zirconium alloy cladding tube caused by excessive oxidation at high temperature is avoided, and therefore, the composite tube can improve the corrosion resistance of the water-resistant side of the fuel rod cladding tube.
Secondly, the dissimilar metal composite tube obtained by the invention has better heat strength than a zirconium alloy cladding tube. According to the zirconium alloy stainless steel dissimilar metal composite pipe, a metallurgical bonding layer is arranged between the zirconium alloy pipe and the stainless steel pipe. The metallurgical bonding layer plays a role in bonding, so that the zirconium alloy and the stainless steel are tightly bonded without gaps, and the high-temperature strength of the stainless steel is superior to that of the zirconium alloy, so that the heat strength of the composite pipe is superior to that of a zirconium alloy pipe.
Thirdly, the dissimilar metal composite pipe obtained by the method has good heat conduction performance. Because the zirconium alloy pipe and the stainless steel pipe in the composite pipe are metallurgically bonded, and no gap exists between the two pipes, the composite pipe has good heat-conducting property.
Therefore, compared with the zirconium alloy cladding tube, the zirconium alloy stainless steel dissimilar metal composite tube has more excellent lateral corrosion resistance and better heat strength, can ensure the structural integrity of the fuel rod at higher temperature, can improve the LOCA accident resistance of the fuel rod, and is suitable for the fuel rod cladding tube of a water-cooled nuclear reactor at higher fuel consumption or higher temperature.
The method and the technical effects of the present invention will be further described in the following with reference to the accompanying drawings to fully understand the objects, features and effects of the present invention.
Drawings
FIG. 1 is a composite tube cross-sectional view of a preferred embodiment of the invention.
FIG. 2 is a schematic view of the end fitting of an extruded tubular blank according to a preferred embodiment of the invention.
FIG. 3 is a schematic representation of a metallurgical bond coat of a composite pipe according to a preferred embodiment of the invention.
Detailed Description
Referring to fig. 1, a cross-sectional view of a composite pipe according to a preferred embodiment of the present invention is shown, wherein the composite pipe comprises an inner pipe 1 and an outer pipe 2. Wherein, the inner layer pipe 1 adopts zirconium alloy, and the outer layer pipe 2 adopts stainless steel. The composite pipe further comprises a metallurgical bonding layer 3 between the inner 1 and outer 2 pipe materials, which contains elements from the inner 1 and outer 2 pipe materials.
The preferred zirconium alloy adopted in the preferred embodiment is preferably Zr-4 alloy, and the thickness of the Zr-4 alloy pipe is 0.35-0.55 mm; the stainless steel is preferably 0Cr18Ni9Ti stainless steel, and the thickness of the stainless steel pipe is 0.15-0.35 mm; the thickness of the metallurgical bonding layer is 0.01mm-0.1 mm. The zirconium alloy stainless steel composite pipe has the thickness of 0.50-0.65 mm, the outer diameter of 8.0-12 mm and the length of 1.0-6.0 m.
The preparation process and the steps of the zirconium alloy stainless steel dissimilar metal composite pipe of the preferred embodiment of the invention are as follows:
(1) preparing a Zr-4 alloy blank into a Zr-4 alloy tube blank by processing;
(2) preparing a 0Cr18Ni9Ti stainless steel blank into a 0Cr18Ni9Ti stainless steel pipe blank through processing;
(3) machining and surface cleaning the two tube blanks to keep the contact surfaces clean;
(4) assembling the two processed tube blanks, as shown in FIG. 2, assembling the stainless steel tube blank (outer layer tube 2) outside the zirconium alloy tube blank (inner layer tube 1), placing into an electron beam welding box, vacuumizing to a vacuum of less than 3 × 10-3Pa, and then carrying out electron beam welding on the end face of the tube blank to keep the gap between the contact surfaces of the tube blank and the tube blank vacuum so as to obtain an extruded tube blank.
(5) And (3) covering the extruded tube blank with an inner covering sleeve and an outer covering sleeve, heating at 1150 ℃ under a vacuum condition, and then extruding on an extruder to obtain the rolled tube blank.
(6) And removing the inner sheath and the outer sheath, cleaning the rolled tube blank, and then obtaining the composite tube through a rolling process. As shown in fig. 3, a metallurgical bonding layer 3 is formed between the zirconium alloy pipe (inner pipe 1) and the stainless steel pipe (outer pipe 2).
Since the 0Cr18Ni9Ti stainless steel of the outer layer has excellent corrosion resistance, particularly shows better corrosion resistance than zirconium alloy in high-temperature and high-pressure water medium, the high-temperature oxidation can be slowed down when LOCA accident happens to the reactor; meanwhile, the high-temperature strength of the 0Cr18Ni9Ti stainless steel is better than that of the zirconium alloy, so the heat strength of the composite pipe is better than that of the zirconium alloy. Therefore, compared with a zirconium alloy cladding tube, the dissimilar metal composite tube has more excellent lateral corrosion resistance and higher heat strength, can improve the LOCA accident resistance of the fuel rod, and is suitable for the fuel rod cladding tube under higher burnup or higher temperature of a nuclear reactor.
The foregoing detailed description of the preferred embodiments of the invention has been presented. It should be understood that numerous modifications and variations could be devised by those skilled in the art in light of the present teachings without departing from the inventive concepts. Therefore, the technical solutions available to those skilled in the art through logic analysis, reasoning and limited experiments based on the prior art according to the concept of the present invention should be within the scope of protection defined by the claims.
Claims (4)
1. The zirconium alloy stainless steel composite pipe for the nuclear fuel element cladding is characterized by comprising an inner layer pipe and an outer layer pipe which are metallurgically bonded, wherein the inner layer pipe is zirconium alloy Zr-4, the outer layer pipe is stainless steel 0Cr18Ni9Ti, the composite pipe further comprises a metallurgical bonding layer positioned between the inner layer pipe and the outer layer pipe, the metallurgical bonding layer contains elements from the inner layer pipe and the outer layer pipe, the thickness of the inner layer pipe is 0.50mm-0.65mm, the thickness of the outer layer pipe is 0.15 mm-0.35 mm, and the thickness of the metallurgical bonding layer is 0.01 mm-0.10 mm;
the preparation method of the composite pipe comprises the following steps:
a) processing a zirconium alloy blank to prepare a zirconium alloy tube blank, wherein the zirconium alloy blank is zirconium alloy Zr-4;
b) processing a stainless steel blank to prepare a stainless steel pipe blank, wherein the stainless steel blank is 0Cr18Ni9Ti stainless steel;
c) assembling a stainless steel pipe blank outside a zirconium alloy pipe blank, putting the stainless steel pipe blank into an electron beam welding box, and vacuumizing, wherein the vacuum pressure is lower than 3 x 10-3Pa, then carrying out electron beam welding on the upper end surfaces and the lower end surfaces of the stainless steel tube blank and the zirconium alloy tube blank to keep the gap between the contact surfaces of the stainless steel tube blank and the zirconium alloy tube blank vacuum to obtain an extruded tube blank;
d) wrapping the extruded tube blank with an inner sheath and an outer sheath, heating under vacuum condition or under the protection of inert gas at 1150 ℃, and then extruding by using an extruder to obtain a rolled tube blank;
e) and removing the inner sheath and the outer sheath, cleaning the rolled tube blank, and then obtaining the zirconium alloy stainless steel composite tube through a rolling process, wherein a metallurgical bonding layer is arranged between the zirconium alloy tube and the stainless steel tube in the zirconium alloy stainless steel composite tube.
2. The nuclear fuel element clad zirconium alloy stainless steel composite tube of claim 1, wherein the metallurgical bond layer comprises elements including one or more of Zr, Fe, Cr, Mn, Sn, Ni, Al, Mo, Co, Nb, Ti, V, Cu, W, O, Si, B, C, N, P, S, Be, Se, and rare earths.
3. The nuclear fuel element clad zirconium alloy stainless steel composite tube of claim 1, wherein the composite tube is produced by machining and surface cleaning the zirconium alloy tube blank and the stainless steel tube blank to maintain clean contact surfaces prior to step c.
4. A nuclear fuel rod using the nuclear fuel element clad zircaloy stainless steel composite tube of claim 1, wherein the nuclear fuel rod includes a fuel core and a clad, the clad being the zircaloy stainless steel composite tube with the zircaloy, the metallurgical bonding layer, and the stainless steel in order from inside to outside, the fuel core being disposed in the zircaloy stainless steel composite tube.
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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. |