High-cr ferritic/martensitic steel having improved creep resistance and preparation method thereof
Inactive Publication Date: 2011-07-07
KOREA ATOMIC ENERGY RES INST +1
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[0014]In one embodiment, a high-Cr ferritic / martensitic steel having an improved creep resistance as a core material for a sodium-cooled fast reactor (SFR) is provided.
[0015]To achieve the above-mentioned objects of the present invention, in one embodiment, a high-Cr ferritic / martensitic steel having improved tensile strength and creep resistance as a material for a sodium-cooled fast reactor (SFR) may include 0.04˜0.13 weight % of carbon, 0.03˜0.07 weight % of silicon, 0.40˜0.50 weight % of manganese, 0.40˜0.50 weight % of nickel, 8.5˜9.5 weight % of chromium, 0.45˜0.55 weight % of molybdenum, 0.10˜0.25 weight % of vanadium, 0.02˜0.10 weight % of tantalum, 0.15˜0.25 weight % of niobium, 1.5˜3.0 weight % of tungsten, 0.05˜0.12 weight % of nitrogen, 0.004˜0.008 weight % of boron and iron balance.
[0016]In another embodiment, a high-Cr ferritic / martensitic steel having improved tensile strength and creep resistance as a material for a sodium-cooled fast reactor (SFR) may include 0.04˜0.13 weight % of carbon, 0.03˜0.07 weight % of silicon, 0.40˜0.50 weight % of manganese, 0.40˜0.50 weight % of nickel, 8.5˜9.5 weight % of chromium, 0.45˜0.55 weight % of molybdenum, 0.10˜0.25 weight % of vanadium, 0.02˜0.10 weight % of tantalum, 0.15˜0.25 weight % of niobium, 1.5˜3.0 weight % of tungsten, 0.05˜0.12 weight % of nitrogen, 0.004˜0.008 weight % of boron, and iron balance, and further include 0.002˜0.010 weight % of phosphorus, or 0.01˜0.08 weight % of zirconium.
[0017]Since high-Cr ferritic / martensitic steel shows improved tensile strength and creep resistance due to adjusted contents of niobium, tantalum, tungsten, nitrogen, boron, zirconium, or carbon, the high-Cr ferritic / martensitic steel can be effectively used as a nuclear material for Generation IV SFR nuclear fuel.
Problems solved by technology
The low radioactive FM steel has the limited options in terms of the alloying elements added to reduce long-lived high level radioactive material generated by fast neutronirradiation.
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example 1
Preparation of High-Cr Ferritic / Martensitic Steels
[0061]As for experimental materials, 0.07 weigh % of carbon, 0.04 weight % of silicon, 0.428 weight % of manganese, 0.460 weight % of nickel, 9.10 weight % of chromium, 0.52 weight % of molybdenum, 0.20 weight % of vanadium, 0.05 weight % of tantalum, 0.20 weight % of niobium, 2.00 weight % of tungsten, 0.083 weight % of nitrogen, 0.0056 weight % of boron, and iron balance were processed in a Vacuum Induction Melting Furnace into a 30 kg of ingot. The ingot was retained at 1150° C. for 2 hours, and achieved hot rolling to a final thickness of 15 mm.
[0062]Heat treatment was then performed as follows.
[0063]To be specific, the alloy was normalized at 1050° C. for 1 hour, and was air-cooled.
[0064]After that, the normalized alloy was tempered at 750° C. for 2 hours and was air-cooled to form a high-Cr ferritic / martensitic steel.
[0065]The high-Cr ferritic / martensitic steel underwent additional heat treatment and cool working which were rep...
example 2
[0066]A high-Cr ferritic / martensitic steel was produced with a method similar to that of Example 1, except that 0.069 weight % of carbon, 0.045 weight % of silicon, 0.445 weight % of manganese, 0.450 weight % of nickel, 8.97 weight % of chromium, 0.49 weight % of molybdenum, 0.203 weight % of vanadium, 0.02 weight % of tantalum, 0.20 weight % of niobium, 2.07 weight % of tungsten, 0.084 weight % of nitrogen, 0.0063 weight % of boron and iron balance were used as experimental materials.
example 3
[0067]Except that 0.069 weight % of carbon, 0.049 weight % of silicon, 0.435 weight % of manganese, 0.447 weight % of nickel, 8.96 weight % of chromium, 0.49 weight % of molybdenum, 0.205 weight % of vanadium, 0.10 weight % of tantalum, 0.19 weight % of niobium, 2.01 weight % of tungsten, 0.086 weight % of nitrogen, 0.006 weight % of boron and iron balance were used as experimental materials, other processes are the same as example 1 to achieve high-Cr ferritic / martensitic steels.
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Abstract
High-Cr ferritic / martensitic steels having an improved tensile strength and creep resistance are provided, which includes 0.04˜0.13 weight % of carbon, 0.03˜0.07 weight % of silicon, 0.40˜0.50 weight % of manganese, 0.40˜0.50 weight % of nickel, 8.5˜9.5 weight % of chromium, 0.45˜0.55 weight % of molybdenum, 0.10˜0.25 weight % of vanadium, 0.02˜0.10 weight % of tantalum, 0.15˜0.25 weight % of niobium, 1.5˜3.0 weight % of tungsten, 0.05˜0.12 weight % of nitrogen, 0.004˜0.008 weight % of boron, and optionally, 0.002˜0.010 weight % of phosphorus or 0.01˜0.08 weight % of zirconium, and iron balance. By regulating the contents of alloying elements such as niobium, tantalum, tungsten, nitrogen, boron, zirconium, carbon, the high-Cr ferritic / martensitic steels with superior tensile strength and creep resistance are provided, and can be effectively used as an in-core structural material for Generation IV sodium-cooled fast reactor (SFR) which is used under high temperature and high irradiation conditions.
Description
CROSS REFERENCE TO RELATED APPLICATIONS[0001]This application claims priority from Korean Patent Application No. 10-2010-0001425, filed on Jan. 7, 2010, in the Korean Intellectual Property Office, the disclosure of which is incorporated herein by reference in its entirety.BACKGROUND OF THE INVENTION[0002]1. Field of the Invention[0003]The invention relates to high-Cr ferritic / martensitic steel having improved creep resistance and a preparation method thereof.[0004]2. Description of the Related Art[0005]The Sodium-Cooled Fast Reactor (SFR) uses a fast neutron, and has nuclear fuel breeding characteristic. Accordingly, since the early stage of nuclear power industry, SFR has been continuously developed mainly for efficient use of uranium resources. As reflected in the Generation IV reactor (Gen IV) development program, the sodium-cooled fast reactor has regained the spotlight for recycling of used nuclear fuels and transmutation of long-lived radionuclide wastes.[0006]Nuclear fuel is ...
Claims
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