Alloy movable conduit for sodium-cooled fast reactor control rod driving mechanism and manufacturing method

A driving mechanism, sodium-cooled fast reactor technology, applied in the control of nuclear reactions, reactors, nuclear power generation, etc., can solve the problems of technical difficulties in smelting and manufacturing, high deformation resistance, high degree of alloying of GH1059 alloy, and improve radiation swelling resistance. performance, the effect of improving corrosion resistance, good microstructure and mechanical properties

Active Publication Date: 2020-11-03
JIANGSU YINHUAN PRECISION STEEL TUBE CO LTD
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0007] GH1059 alloy has a high degree of alloying and high deformation resistance, and its smelting and manufacturing technology is difficult
Although the GH1059 alloy was born in the former Soviet Union, it is basically a "new alloy" for us, and there is no relevant data to support it.

Method used

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  • Alloy movable conduit for sodium-cooled fast reactor control rod driving mechanism and manufacturing method

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Experimental program
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Effect test

Embodiment 1

[0055] An alloy moving conduit for a sodium-cooled fast reactor control rod drive mechanism provided in this embodiment has the following chemical composition and mass percentage: C: 0.063%, Si: 0.10%, Mn: 1.51%, P: 0.005%, S: 0.005%, Cr: 16.44%, Ni: 36.30%, Cu: 0.03%, Mo: 3.40%, W: 0.063%, Al: 0.08%, N: 0.018%, Co: 0.005%, B: 0.0017%, Zr: 0.010%, Y: 0.001%, Sn: 0.0002%, As: 0.0007%, Pb: 0.0001%, Bi: 0.0001%, and the balance is Fe and trace elements.

[0056] The manufacturing method comprises the steps of:

[0057] (1) Smelting

[0058] The alloy material is smelted by vacuum induction at a smelting temperature of 1480°C, cast into an alloy ingot of Ф440mm, and then smelted into an alloy ingot of Ф620 / Ф720mm by using a 6-ton protective atmosphere electroslag remelting furnace;

[0059] (2) Forging

[0060] The alloy ingot obtained in step (1) is opened with a 2,000-ton rapid forging unit, the initial forging temperature is 1100-1150°C, and the final forging temperature is ...

Embodiment 2

[0086] The difference between the alloy moving conduit for the control rod driving mechanism of a sodium-cooled fast reactor provided in this embodiment and the embodiment 1 is that its chemical composition and mass percentage are as follows: C: 0.060%, Si: 0.11%, Mn: 1.53% , P: 0.005%, S: 0.005%, Cr: 16.40%, Ni: 36.30%, Cu: 0.02%, Mo: 3.25%, W: 0.07%, Al: 0.073%, N: 0.02%, Co: 0.005% , B: 0.0019%, Zr: 0.010%, Y: 0.001%, Sn: 0.0002%, As: 0.0008%, Pb: 0.0001%, Bi: 0.0001%, Sb: 0.001%, and the balance is Fe and trace elements.

[0087] The inner and outer surface roughness Ra of the product is ≤1.6μm; the outer diameter is ±1.00mm, the inner diameter is ±1.00mm; the tensile property at 20°C: R m =590MPa, R p0.2 =264MPa, A 50 =49.0%, Z=75%, R m Indicates the tensile strength, R p0.2 Represents the yield strength, A represents the elongation after fracture, Z represents the reduction of area; high temperature tensile properties: at 100°C, R m =553MPa, R p0.2 =233MPa,A 50 =4...

Embodiment 3

[0089] The difference between the alloy moving conduit for the control rod driving mechanism of a sodium-cooled fast reactor provided in this embodiment and the embodiment 1 is that its chemical composition and mass percentage are as follows: C: 0.060%, Si: 0.10%, Mn: 1.54 %, P: 0.005%, S: 0.001%, Cr: 16.27%, Ni: 36.18%, Cu: 0.03%, Mo: 3.26%, W: 0.07%, Al: 0.048%, N: 0.012%, Co: 0.001 %, B: 0.001%, Zr: 0.0010%, Y: 0.001%, Sn: 0.001%, As: 0.0007%, Pb: 0.0001%, Bi: 0.0001%, Sb: 0.001%, and the balance is Fe and trace elements.

[0090] The inner and outer surface roughness Ra of the product is ≤1.6μm; the outer diameter is ±1.00mm, the inner diameter is ±1.00mm; the tensile property at 20°C: R m =592MPa, R p0.2 =266MPa, A 50 =48.5%, Z=75%, R m Indicates the tensile strength, R p0.2 Represents the yield strength, A represents the elongation after fracture, Z represents the reduction of area; high temperature tensile properties: at 100°C, R m =552MPa, R p0.2 =231MPa, A 50 =...

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Abstract

The invention discloses an alloy movable conduit for sodium-cooled fast reactor control rod driving mechanism and a manufacturing method, and relates to iron-nickel-chromium alloy seamless tubes. Thealloy movable conduit comprises the following chemical components including, by mass, 0.04%-0.09% of C, 1.2%-1.8% of Mn, not more than 0.015% of P, not more than 0.010% of S, not more than 0.20% of Si, 15.0%-17.0% of Cr, 35.0%-37.0% of Ni, 3.0%-3.5% of Mo, not more than 0.05% of Cu, not more than 0.05% of Y, not more than 0.002% of B, not more than 0.05% of Zr, not more than 0.1% of Al, not more than 0.2% of W, not more than 0.03% of N, not more than 0.025% of Co, not more than 0.006% of As, not more than 0.005% of Sb, not more than 0.005% of Bi, not more than 0.006% of Sn, not more than 0.006% of Pb, not more than 0.015% of the sum of As, Sb, Bi, Sn and Pb and the balance Fe and trace elements. The alloy movable conduit has the good structure and mechanical properties, corrosion resistance, dimensional precision and surface quality, and the use requirements of a sodium-cooled fast reactor are met.

Description

technical field [0001] The invention relates to the technical field of iron-nickel-chromium alloy seamless pipes, in particular to an alloy moving conduit for a sodium-cooled fast reactor control rod drive mechanism and a manufacturing method thereof. Background technique [0002] As a safe, clean, low-carbon and efficient energy source, nuclear power has always been highly valued. Especially since the Fukushima nuclear accident in Japan in March 2011, the safety of nuclear power has once again become the most important issue for developing countries with nuclear power. At present, nuclear power plants under construction around the world are gradually transitioning to the third-generation nuclear power technology, but the fourth-generation nuclear energy system has become a key research topic for nuclear energy researchers in the coming years. [0003] As early as June 1999, the Office of Nuclear Energy, Science and Technology of the U.S. Department of Energy (DOE) first pro...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C38/04C22C38/02C22C38/58C22C38/44C22C38/42C22C38/50C22C38/54C22C38/46C22C38/52C22C38/06C21D8/10G21C7/12
CPCC21D8/105C22C38/001C22C38/005C22C38/02C22C38/04C22C38/06C22C38/42C22C38/44C22C38/46C22C38/50C22C38/52C22C38/54C22C38/58G21C7/12Y02E30/30
Inventor 高佩王锋朱海涛
Owner JIANGSU YINHUAN PRECISION STEEL TUBE CO LTD
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