阅读说明：本技术 一种核电用gh4169a合金带材的制备方法 (Preparation method of GH4169A alloy strip for nuclear power ) 是由 杨艳 孙光曦 陈韩锋 金建军 王奇 于昂 董生茂 高鸿儒 李渊 余学君 任慧萍 于 2020-05-19 设计创作，主要内容包括：本发明提供了一种核电用GH4169A合金带材的制备方法,包括以下步骤：将电解镍进行真空感应炉熔炼后浇注成电极棒；气氛保护电渣重熔炉制备出合金电渣锭；对合金电渣锭进行均匀化处理和锻造开坯；采用四辊热轧机对板坯进行轧制；采用氩弧焊+填丝的方法进行热轧带卷的拼焊；对拼焊后的合金带卷进行表面抛丸处理、冷轧、精轧、成品热处理,得到核电用GH4169A合金带材。采用本发明方法制备的GH4169A高精度带材,尺寸规格达到0.266mm±0.009mm精度,带材表面无气泡、裂纹、夹杂等缺陷,能够用于制造核反应堆燃料定位格架及保护锆管的弹性元件。(The invention provides a preparation method of a GH4169A alloy strip for nuclear power, which comprises the following steps: smelting the electrolytic nickel in a vacuum induction furnace and then pouring into an electrode bar; preparing an alloy electroslag ingot by an atmosphere protection electroslag remelting furnace; carrying out homogenization treatment and forging cogging on the alloy electroslag ingot; rolling the plate blank by adopting a four-roller hot rolling mill; splicing and welding the hot-rolled coil by adopting an argon arc welding and wire filling method; and performing surface shot blasting treatment, cold rolling, finish rolling and finished product heat treatment on the alloy strip coil subjected to splicing welding to obtain the GH4169A alloy strip for nuclear power. The GH4169A high-precision strip prepared by the method has the size specification of 0.266mm +/-0.009 mm precision, has no defects of bubbles, cracks, inclusions and the like on the surface of the strip, and can be used for manufacturing nuclear reactor fuel spacer grids and elastic elements for protecting zirconium tubes.)

1. A preparation method of a GH4169A alloy strip for nuclear power is characterized by comprising the following steps:

(1) ball-milling electrolytic nickel, smelting in a vacuum induction furnace, and then pouring into an electrode bar;

(2) polishing the surface of the electrode bar obtained in the step (1), and inserting the electrode bar into slag of an electroslag remelting furnace to prepare an alloy electroslag ingot;

(3) carrying out homogenization treatment and forging on the alloy electroslag ingot obtained in the step (2) in sequence to obtain a plate blank;

(4) sequentially carrying out surface polishing and heating on the plate blank obtained in the step (3), and cogging and hot rolling by using a hot rolling mill to obtain a hot rolled strip coil;

(5) carrying out solution heat treatment on the hot rolled strip coil obtained in the step (4) to obtain an alloy strip coil;

(6) welding the alloy strip coil obtained in the step (5);

(7) performing surface shot blasting treatment on the alloy strip coil subjected to the tailor welding in the step (6) by using a shot blasting machine;

(8) performing cold rolling on the alloy strip coil subjected to surface shot blasting treatment in the step (7);

(9) performing finish rolling on the alloy strip coil subjected to the cold rolling in the step (8);

(10) and (4) carrying out finished product heat treatment on the alloy strip coil subjected to finish rolling in the step (9) to obtain the GH4169A alloy strip for nuclear power.

2. The preparation method of the GH4169A alloy strip for nuclear power according to claim 1, wherein the process conditions for vacuum induction furnace smelting of electrolytic nickel in step (1) are as follows: the vacuum degree in the melting period is controlled to be 1.0 Pa-4.0 Pa, the vacuum degree in the refining period is controlled to be 0.3 Pa-1.0 Pa, the refining temperature is 1420 ℃ -1450 ℃, and the refining time is 15 min-20 min.

3. The preparation method of the GH4169A alloy strip for nuclear power according to claim 1, wherein the components and mass percentages of the slag of the electroslag remelting furnace in the step (2) are as follows: al (Al)₂O₃：15％～25％、CaO：10％～25％、MgO：1％～3％、TiO₂: 3 to 6 percent of CaF and the balance of CaF₂(ii) a The process conditions for preparing the alloy electroslag ingot by adopting the electroslag remelting furnace in the step (2) are as follows: under the protection of inert gas, the baking temperature of the molten slag is 720-750 ℃, the baking time of the molten slag is 8-10 h, the arcing current is 800-1000A, the arcing voltage is 40-50V, the formal smelting current is 5000-5300A, the formal smelting voltage is 40-50V, the feeding time is 15-20 min, the power is cut off and the ingot is removed after being cooled for 15-20 min, and the ingot is cooled to the room temperature in the air.

4. The preparation method of the GH4169A alloy strip for nuclear power according to claim 1, wherein in the step (3), the alloy electroslag ingot is subjected to homogenization treatment, and then is forged after being cooled to l 100-l 130 ℃ along with an electroslag remelting furnace and being kept warm for 2-3 hours; the homogenization treatment comprises primary homogenization treatment and secondary homogenization treatment, and the process conditions of the primary homogenization treatment are as follows: the primary homogenization temperature is 1150-1160 ℃, the primary homogenization time is 25-30 hours, and the process conditions of the secondary homogenization treatment are as follows: the secondary homogenization temperature is 1180-1190 ℃, and the secondary homogenization time is 30-35 hours; the forging process conditions are as follows: the final forging temperature is 930-950 ℃, the alloy electroslag ingot is forged into a plate blank, and the plate blank is cooled to room temperature in the air.

5. The preparation method of the GH4169A alloy strip for nuclear power according to claim 1, wherein the process conditions for heating the slab in the step (4) are as follows: heating at 1150-1160 deg.c for 1.0-1.5 hr, and cogging hot rolling in a four-roller reversing hot rolling mill.

6. The method for preparing the GH4169A alloy strip for nuclear power according to claim 1, wherein the solution heat treatment of the hot-rolled strip coil in the step (5) is carried out under the following process conditions: heating temperature is 1100-1130 ℃, heat preservation time is 1.5-2.0 hours, and water cooling is rapidly carried out after heating is finished.

7. The preparation method of the GH4169A alloy strip for nuclear power as claimed in claim 1, wherein in step (6), the alloy strip coil subjected to solution heat treatment is subjected to tailor welding by argon arc welding and wire filling, and the filled wire is GH4169 wire with the diameter of 1.6-2.0 mm or Cr20Ni80 wire with the diameter of 1.6-2.0 mm.

8. The preparation method of the GH4169A alloy strip for nuclear power as claimed in claim 1, wherein the cold rolling of the alloy strip coil subjected to surface blasting in step (8) includes 2 rolling passes, the processing rate of the alloy strip coil subjected to surface blasting in each rolling pass is 45% -52%, the alloy strip coil subjected to surface blasting is subjected to bright annealing between the 2 rolling passes, and the bright annealing process conditions of the alloy strip coil subjected to surface blasting are as follows: the annealing temperature is 980-1000 ℃, the annealing speed is 1.0-1.2 m/min, and the annealing atmosphere is ammonia decomposition gas.

9. The preparation method of the GH4169A alloy strip for nuclear power as claimed in claim 1, wherein the cold-rolled alloy strip coil in step (9) is subjected to a twenty-high mill finish rolling, the finish rolling comprises 5 rolling passes, the reduction ratio of the cold-rolled alloy strip coil in each rolling pass is 35% -40%, the bright annealing is performed on the cold-rolled alloy strip coil between the rolling passes, and the bright annealing process conditions of the cold-rolled alloy strip coil are as follows: the annealing temperature is 980-1000 ℃, the annealing speed is 0.8-1.0 m/min, and the annealing atmosphere is ammonia decomposition gas.

10. The preparation method of the GH4169A alloy strip for nuclear power as claimed in claim 1, wherein the process conditions for performing the finish heat treatment on the finish-rolled alloy strip coil in the step (10) are as follows: the annealing heating temperature is 980-1000 ℃, the annealing speed is 0.8-1.0 m/min, and the annealing atmosphere is pure hydrogen.

11. The preparation method of the nuclear power GH4169A alloy strip according to claim 1, wherein the nuclear power GH4169A alloy strip obtained in the step (10) comprises the following components in percentage by mass: 50.0 to 55.0 percent of Ni, 17.0 to 21.0 percent of Cr17, 0.015 to 0.06 percent of C, 2.80 to 3.30 percent of Mo, 4.75 to 5.50 percent of Nb, 0.75 to 1.15 percent of Ti0, 0.30 to 0.70 percent of Al, less than or equal to 0.35 percent of Si, less than or equal to 0.35 percent of Mn, less than or equal to 0.015 percent of P, less than or equal to 0.015 percent of S, less than or equal to 0.006 percent of B, less than or equal to 0.10 percent of Ta, less than or equal to 1.0 percent of Co, less than or; the thickness of the GH4169A alloy strip for nuclear power obtained in the step (10) is 0.266mm +/-0.009 mm.

Technical Field

The invention belongs to the field of metal material processing, and particularly relates to a preparation method of a GH4169A alloy strip for nuclear power.

Background

The GH4169 alloy belongs to precipitation hardening type wrought superalloy, has excellent mechanical property, higher yield strength and tensile strength when being used below 700 ℃, good thermoplasticity and long-term structure stability, and becomes a key material for a large number of applications in the fields of aviation, aerospace, nuclear energy and petrochemical industry.

In recent years, with the rapid development of national nuclear power technology, GH4169 alloy cold-rolled sheet and strip products are widely applied to nuclear reactor fuel assemblies. The GH4169 alloy adopted at different parts in the reactor is different in product types, for example, a strip with the thickness of about 0.3mm is used for a nuclear reactor fuel positioning grid, wires with the diameter of 0.3-10 mm and round rods are used as nuclear equipment welding materials or driving rod spring wire materials, a cold-drawn seamless pipe material is used for a U-shaped sealing ring of a reactor pressure container, and an anti-irradiation compression spring is a cold-drawn wire material or a special-shaped material. The GH4169 strip for the nuclear power field has higher technical requirements on the aspects of product surface quality, mechanical property, specification and size precision and the like.

At present, the country is building nuclear power 'hualong one', some provinces are developing new energy industries such as onshore nuclear power, and with the continuous improvement of the independent innovation capability of nuclear power technology, the localization of nuclear power materials is very important. GH4169 is a fuel spacer grid and elastic element protecting the zirconium tubes in nuclear reactors, and is currently still in the inlet. The successful development of the GH4169 strip provides guarantee for national nuclear power construction and technical export, and has important strategic significance.

Disclosure of Invention

The invention aims to solve the technical problem of providing a preparation method of a GH4169A high-precision strip for nuclear power, and the method can be used for preparing the high-precision GH4169A strip which has the size specification of 0.266mm +/-0.009 mm, the tensile strength of 1462 MPa-1614 MPa in a solid solution + aging state, the yield strength of 1252 MPa-1350 MPa, the elongation after fracture of 12.6-15.1 percent, the grain size of the strip of 6-7 grades and no defects of bubbles, cracks, inclusions and the like on the surface of the strip, and is used for manufacturing a nuclear reactor fuel positioning grid and an elastic element for protecting a zirconium tube.

The invention adopts the following technical scheme:

a preparation method of a GH4169A alloy strip for nuclear power is characterized by comprising the following steps:

(1) ball-milling electrolytic nickel, smelting in a vacuum induction furnace, and then pouring into an electrode bar;

(2) polishing the surface of the electrode bar obtained in the step (1), and inserting the electrode bar into slag of an electroslag remelting furnace to prepare an alloy electroslag ingot;

(3) carrying out homogenization treatment and forging on the alloy electroslag ingot obtained in the step (2) in sequence to obtain a plate blank;

(4) sequentially carrying out surface polishing and heating on the plate blank obtained in the step (3), and cogging and hot rolling by using a hot rolling mill to obtain a hot rolled strip coil;

(5) carrying out solution heat treatment on the hot rolled strip coil obtained in the step (4) to obtain an alloy strip coil;

(6) welding the alloy strip coil obtained in the step (5);

(7) performing surface shot blasting treatment on the alloy strip coil subjected to the tailor welding in the step (6) by using a shot blasting machine;

(8) performing cold rolling on the alloy strip coil subjected to surface shot blasting treatment in the step (7);

(9) performing finish rolling on the alloy strip coil subjected to the cold rolling in the step (8);

(10) and (4) carrying out finished product heat treatment on the alloy strip coil subjected to finish rolling in the step (9) to obtain the GH4169A alloy strip for nuclear power.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the process conditions for carrying out vacuum induction furnace smelting on electrolytic nickel in the step (1) are as follows: the vacuum degree in the melting period is controlled to be 1.0 Pa-4.0 Pa, the vacuum degree in the refining period is controlled to be 0.3 Pa-1.0 Pa, the refining temperature is 1420 ℃ -1450 ℃, and the refining time is 15 min-20 min.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the components and mass percentages of the slag of the electroslag remelting furnace in the step (2) are as follows: al (Al)₂O₃：15％～25％、CaO：10％～25％、MgO：1％～3％、TiO₂: 3 to 6 percent of CaF and the balance of CaF₂(ii) a The process conditions for preparing the alloy electroslag ingot by adopting the electroslag remelting furnace in the step (2) are as follows: under the protection of inert gas, the baking temperature of the molten slag is 720-750 ℃, the baking time of the molten slag is 8-10 h, the arcing current is 800-1000A, the arcing voltage is 40-50V, the formal smelting current is 5000-5300A, the formal smelting voltage is 40-50V, the feeding time is 15-20 min, the power is cut off and the ingot is removed after being cooled for 15-20 min, and the ingot is cooled to the room temperature in the air.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the alloy electroslag ingot in the step (3) is subjected to homogenization treatment, cooled to l 100-l 130 ℃ along with an electroslag remelting furnace, and subjected to heat preservation for 2-3 hours and then forged; the homogenization treatment comprises primary homogenization treatment and secondary homogenization treatment, and the process conditions of the primary homogenization treatment are as follows: the primary homogenization temperature is 1150-1160 ℃, the primary homogenization time is 25-30 hours, and the process conditions of the secondary homogenization treatment are as follows: the secondary homogenization temperature is 1180-1190 ℃, and the secondary homogenization time is 30-35 hours; the forging process conditions are as follows: the final forging temperature is 930-950 ℃, the alloy electroslag ingot is forged into a plate blank, and the plate blank is cooled to room temperature in the air.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the technological conditions for heating the slab in the step (4) are as follows: heating at 1150-1160 deg.c for 1.0-1.5 hr, and cogging hot rolling in a four-roller reversing hot rolling mill.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the process conditions for carrying out solution heat treatment on the hot-rolled strip coil in the step (5) are as follows: heating temperature is 1100-1130 ℃, heat preservation time is 1.5-2.0 hours, and water cooling is rapidly carried out after heating is finished.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that in the step (6), the alloy strip coil subjected to solution heat treatment is subjected to tailor-welding in an argon arc welding and wire filling mode, and the filled wire is GH4169 wire with the diameter of 1.6-2.0 mm or Cr20Ni80 wire with the diameter of 1.6-2.0 mm.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the cold rolling of the alloy strip coil subjected to surface blasting in the step (8) comprises 2 rolling passes, the machining rate of the alloy strip coil subjected to surface blasting in each rolling pass is 45-52%, bright annealing is performed on the alloy strip coil subjected to surface blasting between the 2 rolling passes, and the bright annealing process conditions of the alloy strip coil subjected to surface blasting are as follows: the annealing temperature is 980-1000 ℃, the annealing speed is 1.0-1.2 m/min, and the annealing atmosphere is ammonia decomposition gas.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the alloy strip coil subjected to cold rolling in the step (9) is subjected to finish rolling in a twenty-high mill, the finish rolling comprises 5 rolling passes, the working ratio of the alloy strip coil subjected to cold rolling in each rolling pass is 35% -40%, bright annealing is performed on the alloy strip coil subjected to cold rolling between the rolling passes, and the bright annealing process conditions of the alloy strip coil subjected to cold rolling are as follows: the annealing temperature is 980-1000 ℃, the annealing speed is 0.8-1.0 m/min, and the annealing atmosphere is ammonia decomposition gas.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the process conditions of the finish-rolled alloy strip coil in the step (10) for heat treatment of the finished product are as follows: the annealing heating temperature is 980-1000 ℃, the annealing speed is 0.8-1.0 m/min, and the annealing atmosphere is pure hydrogen.

The preparation method of the GH4169A alloy strip for nuclear power is characterized in that the GH4169A alloy strip for nuclear power obtained in the step (10) comprises the following components in percentage by mass: 50.0 to 55.0 percent of Ni, 17.0 to 21.0 percent of Cr, 0.015 to 0.06 percent of C, 2.80 to 3.30 percent of Mo, 4.75 to 5.50 percent of Nb, 0.75 to 1.15 percent of Ti, 0.30 to 0.70 percent of Al, less than or equal to 0.35 percent of Si, less than or equal to 0.35 percent of Mn, less than or equal to 0.015 percent of P, less than or equal to 0.015 percent of S, less than or equal to 0.006 percent of B, less than or equal to 0.10 percent of Ta, less than or equal to 1.0 percent of Co, less than or equal to; the thickness of the GH4169A alloy strip for nuclear power obtained in the step (10) is 0.266mm +/-0.009 mm.

The invention has the beneficial technical effects that:

1) in the preparation process of the GH4169A strip, the vacuum induction melting and atmosphere protection electroslag remelting duplex refining process is adopted, so that the purity of the alloy can be effectively improved, the impurity content is reduced, the remelted alloy is compact in structure, and the quality and the hot-working performance of the alloy ingot are improved.

2) The carbon content is optimized in the alloy chemical composition design process, the carbon content is controlled to be 0.015-0.06%, the content of carbide in the alloy is ensured, and the alloy achieves the due service performance.

3) The invention combines the homogenization heat treatment of the electroslag ingot with the forging heating, thereby not only saving energy consumption, but also ensuring the heat permeability of the alloy and improving the heat deformation performance of the alloy.

4) In the splicing welding procedure of the hot rolled strip coil, the argon arc welding and wire filling mode is adopted for welding, so that the mechanical property of a welding line can be improved, and the problem of strip breakage in the subsequent rolling process is effectively solved.

5) The invention optimizes the processing rate of each rolling process in the cold rolling process, simultaneously adopts a pure hydrogen bright annealing mode, optimizes the annealing temperature and the annealing speed, and ensures that the alloy strip has good surface quality, mechanical property and dimensional precision.

6) The GH4169A strip prepared by the method has the size specification of 0.266mm +/-0.009 mm, the tensile strength of 1462 MPa-1614 MPa in the solid solution and aging state, the yield strength of 1252 MPa-1350 MPa, the elongation after fracture of 12.6% -15.1% and the grain size of the strip of 6-7 levels, has no defects of bubbles, cracks, inclusions and the like on the surface of the strip, and can be used for manufacturing fuel spacer grids of nuclear reactors and elastic elements for protecting zirconium tubes.

Drawings

FIG. 1 is the grain structure of GH4169A strip with a thickness of 0.266mm prepared in example 1;

FIG. 2 shows the grain structure of GH4169A strip with a thickness of 0.264mm prepared in example 2.

Detailed Description

The invention discloses a preparation method of a GH4169A alloy strip for nuclear power, which is characterized by comprising the following steps:

(1) vacuum induction melting: ball-milling electrolytic nickel, smelting in a vacuum induction furnace, and then pouring into an electrode bar; the process conditions for carrying out vacuum induction furnace smelting on the electrolytic nickel in the step (1) are as follows: the vacuum degree in the melting period is controlled to be 1.0 Pa-4.0 Pa, the vacuum degree in the refining period is controlled to be 0.3 Pa-1.0 Pa, the refining temperature is 1420 ℃ -1450 ℃, and the refining time is 15 min-20 min.

(2) Electroslag remelting: polishing the surface of the electrode bar obtained in the step (1), and inserting the electrode bar into slag of an electroslag remelting furnace to prepare an alloy electroslag ingot; the slag of the electroslag remelting furnace in the step (2) comprises the following components in percentage by mass: al (Al)₂O₃：15％～25％、CaO：10％～25％、MgO：1％～3％、TiO₂: 3 to 6 percent of CaF and the balance of CaF₂(ii) a And (3) in the step (2), the alloy electroslag ingot is prepared by adopting an electroslag remelting furnace under the protection of inert gas. The process conditions for preparing the alloy electroslag ingot by adopting the electroslag remelting furnace are as follows: the baking temperature of the slag is 720-750 ℃, the baking time of the slag is 8-10 h, the arcing current is 800A-1000A, the arcing voltage is 40V-50V, the formal smelting current is 5000A-5300A, the formal smelting voltage is 40V-50V, the feeding time is 15-20 min, the power is cut off and the ingot is removed after 15-20 min, and the ingot is cooled to the room temperature in the air.

(3) Homogenizing heat treatment and forging cogging of alloy electroslag ingots: carrying out homogenization heat treatment and forging heating on the alloy electroslag ingot obtained in the step (2) together to obtain a plate blank; after the alloy electroslag ingot in the step (3) is subjected to homogenization treatment, the alloy electroslag ingot is cooled to l 100-l 130 ℃ along with an electroslag remelting furnace, and is forged after being kept for 2-3 hours; the homogenization treatment comprises primary homogenization treatment and secondary homogenization treatment, and the process conditions of the primary homogenization treatment are as follows: the primary homogenization temperature is 1150-1160 ℃, the primary homogenization time is 25-30 hours, and the process conditions of the secondary homogenization treatment are as follows: the secondary homogenization temperature is 1180-1190 ℃, and the secondary homogenization time is 30-35 hours; the forging process conditions are as follows: the final forging temperature is 930-950 ℃, the alloy electroslag ingot is forged into a plate blank, and the plate blank is cooled to room temperature in the air.

(4) Hot rolling and cogging: sequentially carrying out surface polishing and flaw detection on the plate blank obtained in the step (3), heating, and cogging and hot rolling by using a hot rolling mill to obtain a hot rolled strip coil; the technological conditions for heating the slab in the step (4) are as follows: heating at 1150-1160 deg.c for 1.0-1.5 hr, and cogging hot rolling in a four-roller reversing hot rolling mill. The rolling pass is 60mm → 52mm → 38mm → 26.5mm → 17mm → 11mm → 7.6mm → 5.5 mm.

(5) Solution annealing: carrying out solution heat treatment on the hot rolled strip coil obtained in the step (4) to obtain an alloy strip coil; the process conditions for carrying out the solution heat treatment on the hot-rolled strip coil in the step (5) are as follows: heating temperature is 1100-1130 ℃, heat preservation time is 1.5-2.0 hours, and water cooling is rapidly carried out after heating is finished.

(6) Splicing and welding a coil: welding the alloy strip coil obtained after annealing in the step (5); and (6) splicing and welding the alloy strip coil subjected to the solution heat treatment in an argon arc welding and wire filling mode, wherein the filled wire is GH4169 wire with the diameter of 1.6-2.0 mm or Cr20Ni80 wire with the diameter of 1.6-2.0 mm.

(7) Shot blasting on the surface of the strip coil: and (4) performing surface shot blasting treatment on the alloy strip coil subjected to the tailor welding in the step (6) by using a shot blasting machine to remove surface oxide skin.

(8) And (3) cold rolling with four rollers: cold rolling the alloy strip coil subjected to surface shot blasting treatment in the step (7) by adopting a four-roller cold rolling mill; the cold rolling of the alloy strip coil subjected to surface shot blasting treatment in the step (8) comprises 2 rolling passes, the machining rate of the alloy strip coil subjected to surface shot blasting treatment in each rolling pass is 45-52%, bright annealing is performed on the alloy strip coil subjected to surface shot blasting treatment between the 2 rolling passes to eliminate machining hardening, and the bright annealing process conditions of the alloy strip coil subjected to surface shot blasting treatment are as follows: the annealing temperature is 980-1000 ℃, the annealing speed is 1.0-1.2 m/min, and the annealing atmosphere is ammonia decomposition gas.

(9) Twenty-roller cold rolling: performing finish rolling on the alloy strip coil subjected to the cold rolling in the step (8); and (3) performing finish rolling on the alloy strip coil subjected to the cold rolling in the step (9) by a twenty-high rolling mill, wherein the finish rolling comprises 5 rolling passes, the processing rate of the alloy strip coil subjected to the cold rolling in each rolling pass is 35-40%, bright annealing is performed on the alloy strip coil subjected to the cold rolling between the rolling passes to eliminate work hardening, and the bright annealing process conditions of the alloy strip coil subjected to the cold rolling are as follows: the annealing temperature is 980-1000 ℃, the annealing speed is 0.8-1.0 m/min, and the annealing atmosphere is ammonia decomposition gas.

(10) And (3) heat treatment of a finished product: and (4) carrying out finished product heat treatment on the alloy strip coil subjected to finish rolling in the step (9) to obtain the GH4169A alloy strip for nuclear power. The process conditions for carrying out finished product heat treatment on the alloy strip coil subjected to finish rolling in the step (10) are as follows: the annealing heating temperature is 980-1000 ℃, the annealing speed is 0.8-1.0 m/min, and the annealing atmosphere is pure hydrogen (the dew point is less than or equal to-51 ℃). The GH4169A alloy strip for nuclear power obtained in the step (10) comprises the following components in percentage by mass: 50.0 to 55.0 percent of Ni, 17.0 to 21.0 percent of Cr, 0.015 to 0.06 percent of C, 2.80 to 3.30 percent of Mo, 4.75 to 5.50 percent of Nb, 0.75 to 1.15 percent of Ti, 0.30 to 0.70 percent of Al, less than or equal to 0.35 percent of Si, less than or equal to 0.35 percent of Mn, less than or equal to 0.015 percent of P, less than or equal to 0.015 percent of S, less than or equal to 0.006 percent of B, less than or equal to 0.10 percent of Ta, less than or equal to 1.0 percent of Co, less than or equal to. The thickness of the GH4169A alloy strip for nuclear power obtained in the step (10) is 0.266mm +/-0.009 mm, the carbon content is required to be 0.015-0.06%, the carbide content in the alloy is ensured, and the mechanical properties of the GH4169A alloy strip for nuclear power obtained are as follows: the tensile strength of the solid solution and the aging state is 1462MPa to 1614MPa, the yield strength is 1252MPa to 1350MPa, the elongation after fracture is 12.6 percent to 15.1 percent, and the grain size of the strip is 6 grade to 7 grade.