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New austenite stainless steel material of fuel cladding in supercritical water cooled reactor, and manufacturing process thereof

A technology of austenitic stainless steel and supercritical water, which is used in the reduction of greenhouse gases, instruments, surveying and mapping, and navigation, etc. There are no relevant experimental results in the irradiation performance, and the effects of inhibiting the migration and aggregation of voids, inhibiting irradiation swelling, and fine grains can be achieved.

Active Publication Date: 2012-12-05
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

At present, the mature austenitic stainless steels such as 316Ti, 310S, TP347HFG, and HR3C have different problems under supercritical conditions. For example, 316Ti has good high-temperature strength and radiation resistance, but high-temperature corrosion resistance Does not meet the requirements; 310S has good high temperature strength and corrosion resistance, and its radiation swelling resistance is very poor; TP347HFG has good high temperature strength, but the high temperature corrosion resistance does not meet the requirements, and the radiation performance of the material is not good enough There are relevant experimental results; and HR3C also has good high temperature strength, but the radiation performance is unknown
[0003]At present, these mature austenitic stainless steels cannot fully meet the requirements of the environmental conditions of the fourth-generation nuclear reactor supercritical working conditions. The new austenitic stainless steel cladding material required is imperative
[0004] After searching, there is no report on new austenitic stainless steel cladding materials and specific preparation processes that can meet the requirements of supercritical conditions

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0069] Step 1 Ingredients

[0070] To manufacture the new austenitic stainless steel material in this example, the ingredients used are: Si: 1.5%, Mn: 2.0%, Ti: 0.8%, Nb: 0.6%, Y: 0.01%, Cr: 26%, Ni: 22% , and the balance is high-purity iron Fe; plus 0.05% of the weight of the new material alloy deoxidizer Ca;

[0071] Step 2 Crucible and mold degassing

[0072] Place the magnesia crucible and thin-walled 45# steel mold in a vacuum high-temperature drying oven, heat to 200°C, and keep it warm for 10 hours to degas;

[0073] Step 3 Vacuum induction melting

[0074] Take out the degassed magnesia crucible and the thin-walled 45# steel casting mold from the high-temperature drying oven, first put the ingredients Fe, Cr and Ni into the magnesia crucible, open the vacuum induction furnace door, and sequentially place the casting The mold and the crucible with Fe, Cr and Ni ingredients are placed at the bottom and middle of the vacuum induction furnace, and then the ingredients S...

Embodiment 2

[0087] Step 1 Ingredients

[0088] The alloy ingredients are: Si: 0.1%, Mn: 0.1%, Ti: 0.03%, Nb: 1.0%, Y: 0.5%, Cr: 35%, Ni: 35%, and the balance is high-purity iron Fe; plus this new material Alloy weight 0.07% deoxidizer Ca;

[0089] Step 2 Crucible and mold degassing

[0090] Place the magnesia crucible and thin-walled 45# steel mold in a vacuum high-temperature drying oven and heat to 1200°C, and keep it warm for 1 hour to degas;

[0091] Step 3 Vacuum induction melting

[0092] The melting temperature is 1600°C, the pouring temperature is 1650°C, and the rest are the same as in Example 1;

[0093] Step 4 Arc Melting

[0094]The process is the same as the real example 1, the difference is that the alloy ingot is prepared by smelting at a voltage of 35V and a current of 2000A after the arc is energized;

[0095] Step five forging

[0096] The alloy ingot is forged at a temperature of 1150°C, and the forging ratio is 1.5;

[0097] Step 6 hot rolling

[0098] The forg...

Embodiment 3

[0105] Step 1 Ingredients

[0106] The alloy ingredients are: Si: 0.5%, Mn: 0.6%, Ti: 1.0%, Nb: 0.01%, Y: 0.08%, Cr: 30%, Ni: 12%, and the balance is high-purity iron Fe; plus this new material Alloy weight 0.08% deoxidizer Ca;

[0107] Step 2 Crucible and mold degassing

[0108] Place the magnesia crucible and the thin-walled 45# steel mold in a vacuum high-temperature drying oven and heat to 1000°C, keep it warm for 2 hours for degassing;

[0109] Step 3 Vacuum induction melting

[0110] The melting temperature is 1400°C, the pouring temperature is 1450°C, and the rest are the same as in Example 1;

[0111] Step 4 Arc Melting

[0112] Remove the riser from the ingot, forge it into a Φ50mm round bar at 950°C, and make it into a consumable electrode after polishing; weld the electrode on the auxiliary electrode of a 10Kg vacuum consumable electric arc furnace by argon arc welding, and use Φ100mm crucible, vacuum to 10 -2 Pa, then leak detection, to ensure that the leakag...

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PUM

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Abstract

The invention provides a new austenite stainless steel material of a fuel cladding in a supercritical water cooled reactor, and a manufacturing process thereof. The new austenite stainless steel material is manufactured by adding trace alloy elements Ti (0.03-1%), Nb or Zr (0.01-1%) and Y (0.01-0.5%) to tradition austenite stainless steel and carrying out processes of alloy smelting, casting, forging, heat treatment, rolling, and grain refining treatment. The new austenite stainless steel material of the present invention has the following characteristics that: a tensile strength and a yield strength are respectively 300 MPa and 110 MPa at a temperature of 700 DEG C; mechanical properties and corrosion resistance of the alloy are increased while irradiation swelling resistance of the alloy is substantially improved; excellent performances of high temperature resistance, corrosion resistance and irradiation swelling resistance are provided; the technical key point that the austenite stainless steel fuel cladding in the four generation supercritical water cooled reactor must meet the supercritical operating condition requirements is solved so as to provide basic guarantee for safe operation of the supercritical water cooled reactor core.

Description

technical field [0001] The invention relates to a nuclear reactor structural material and a manufacturing process thereof, in particular to a new austenitic stainless steel material for fuel cladding in a supercritical water-cooled nuclear reactor and a manufacturing process thereof. Background technique [0002] Supercritical water-cooled reactor is the fourth-generation nuclear reactor, which has the advantages of high thermal efficiency, simplified structure, good safety, and good economy. Its fuel cladding material is the key technology of supercritical water-cooled reactor. At present, the supercritical water-cooled reactor cladding materials that are concerned at home and abroad are mainly divided into two categories: nickel-based alloys and austenitic stainless steels. Austenitic stainless steels are popular candidates for fuel cladding due to the low neutron economy due to the high nickel content in nickel-based alloys. However, under the operating conditions of sup...

Claims

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Application Information

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IPC IPC(8): C22C38/58C22C38/50G21C3/07
CPCY02E30/40Y02E30/30
Inventor 潘钱付唐睿刘超紅蒋明忠易伟熊茹王录全刘睿睿
Owner NUCLEAR POWER INSTITUTE OF CHINA