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3ni-1.6cr-0.5mo welding rod for supporting steel for nuclear power equipment and its preparation method

A welding rod and equipment technology, applied in the field of high-strength welding rods, can solve the problem that welding materials are not easy to obtain, and achieve the effects of good welding adaptability, smooth welding rod surface and good manufacturability

Active Publication Date: 2022-03-08
CFHI DALIAN HYDROGENANT REACTOR +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] However, due to the advanced nature and scientific frontier of SA508Gr.4N steel, it can meet the needs of nuclear container welding at home and abroad, and has high strength, high toughness, and good low temperature plasticity (RT NDT ≤-60℃) welding materials are not easy to obtain

Method used

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  • 3ni-1.6cr-0.5mo welding rod for supporting steel for nuclear power equipment and its preparation method
  • 3ni-1.6cr-0.5mo welding rod for supporting steel for nuclear power equipment and its preparation method
  • 3ni-1.6cr-0.5mo welding rod for supporting steel for nuclear power equipment and its preparation method

Examples

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Effect test

example 1

[0018] Example 1, a high-alkalinity and low-hydrogen coating of this embodiment, the solid component and the liquid component in the coating are mixed, and the added weight of the liquid component is 20% of the weight of the solid component. %; The solid component comprises the following components in parts by weight: CaC0 45 parts of CaF 20 parts of TiO 7 parts of Na2CO 1 part of CaSiO 6 parts of MgO 3 parts of TiFe 6 parts of SiFe 2 parts of metal Ni powder 6 parts of metal Cr powder 4 parts ; The low alloy steel welding core used, the weight percentage of chemical composition measured by chemical analysis method: C 0.12%, Si 0.20%, Mn 1.8%, P0.008%, S0.003%, Cr1.6%, Ni 3.0%, Mo0.5%, Cu 0.01%, Co0.002%, B≤0.0005%, Nb≤0.01%, As 0.004%, Sn 0.003%, and the balance is Fe. The liquid component used is potassium sodium 1:1 water glass with 46Be at 20°C.

[0019] After mixing the raw materials of the coating above evenly, sieve it with a 40-mesh sieve to 100% below 40 mesh, stir t...

Embodiment 2

[0027] A high-alkalinity and low-hydrogen coating in this embodiment is formed by mixing solid components and liquid components in the coating, and the added weight of the liquid component is 22% of the weight of the solid component; Said solid components include the following components in parts by weight: CaCO 47 parts of CaF 23 parts of TiO 7 parts of NaCO 1 part of CaSiO 4 parts of MgO 3 parts of TiFe 7 parts of SiFe 2 parts of metal Ni powder 5 parts of metal Cr powder 4 parts; Low-alloy steel welding core, the weight percentage of chemical composition measured by chemical analysis method: C 0.13%, Si 0.19%, Mn 1.6%, P0.006%, S0.003%, Cr1.75%, Ni 3.2%, Mo0. 5%, Cu 0.01%, Co 0.001%, B≤0.0005%, Nb≤0.01%, As 0.003%, Sn 0.003%, and the balance is Fe. The liquid component used is potassium sodium 1:1 water glass with 46Be at 20°C

[0028] After mixing the raw materials of the coating above evenly, sieve through a 40-mesh sieve to 100% below 40 mesh, stir the dry powder evenly...

Embodiment 3

[0036] A high-alkalinity and low-hydrogen coating in this embodiment is formed by mixing solid components and liquid components in the coating, and the added weight of the liquid component is 23% of the weight of the solid component; Said solid components include the following components in parts by weight: CaCO 48 parts of CaF 24 parts of TiO 8 parts of NaCO 1 part of CaSiO 5 parts of MgO 2 parts of TiFe 10 parts of SiFe 1 part of metal Ni powder 4 parts of metal Cr powder 3 parts; Low-alloy steel welding core, the weight percentage of chemical composition measured by chemical analysis method: C 0.13%, Si 0.19%, Mn 1.6%, P0.006%, S0.003%, Cr1.75%, Ni 3.2%, Mo0. 5%, Cu 0.01%, Co 0.001%, B≤0.0005%, Nb≤0.01%, As 0.003%, Sn 0.003%, and the balance is Fe. The liquid component used is potassium sodium 1:1 water glass with 46Be at 20°C.

[0037] After mixing the raw materials of the coating above evenly, sieve through a 40-mesh sieve to 100% below 40 mesh, stir the dry powder evenl...

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Abstract

The invention discloses a 3Ni‑1.6Cr‑0.5Mo welding rod for supporting steel for nuclear power equipment, including a high-alkaline electrode coating and a low-alloy steel welding core for the welding rod. The coating is formed by mixing solid components and liquid components, and the solid The constituent elements and their weight percentages of the components include: CaC03: 44% to 48%, CaF2: 20% to 25%, Ti02: 6% to 8%, Na2CO3: 0 to 1%, CaSi03: 4% to 6%, MgO: 1% to 3%, TiFe: 4% to 10%, SiFe: 1% to 3%, and metal powder containing Ni and Cr: 4% to 10%, Ni in metal powder: 3% to 6%, Cr : 2% to 4%; the liquid component is potassium sodium water glass, which accounts for 20% to 23% of the mass of the dry powder component of mineral raw materials. The constituent elements and weight percentages of the welding core include: C: 0.09% to 0.12%, Si: 0.1%~0.23%, Mn: 1.5%~2.0%, P≤0.02%, S≤0.02%, Cr: 1.0%~1.8%, Ni: 2.6%~3.5%, Mo: 0.3%~0.7%, Cu≤ 0.020%, Co≤0.020%, and the balance is Fe. The electrode has good welding adaptability, high strength of deposited metal, good toughness, and good low-temperature plasticity, which meets the welding requirements of the current development of SA508Gr.4N steel and its improved steel.

Description

technical field [0001] The invention relates to the field of welding materials, in particular to a high-strength welding rod for supporting 3Ni-1.6Cr-0.5Mo steel used in a new generation of nuclear power equipment. Background technique [0002] At present, nuclear power technology has been developed to the second generation, third generation and third generation +. With the development of nuclear power technology, the internal environment of the reactor is becoming more and more severe. For example, the design pressure of the supercritical water-cooled reactor pressure vessel in the fourth-generation reactor type is 27.5MPa, the design temperature of the main chamber is 350°C, and the design temperature of the outlet chamber is 550°C. The design life is 60 years, so the requirements for materials are becoming more and more stringent. At present, the general steel for nuclear reactor pressure vessels in various countries is 620MPa grade SA508-3 steel, but its hardenability, ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B23K35/30B23K35/365B23K35/40
CPCB23K35/3066B23K35/3602B23K35/365B23K35/404B23K35/0272
Inventor 高蕊张秀海王富铭刘学利段莉蕾李兆峰
Owner CFHI DALIAN HYDROGENANT REACTOR
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