Reduced activation Fe-Cr-Mn austenitic steels for nuclear power plants

被引：11
作者：
Demina E.V. [1 ]
Prusakova M.D. [1 ]
Roshchin V.V. [2 ]
N. A. Vinogradova [1 ]
Orlova G.D. [1 ]
机构：
[1] Baikov Institute of Metallurgy and Materials Science, Russian Academy of Sciences, Moscow
[2] OAO NIKIMT-Atomstroi, Moscow
来源：
Inorganic Materials: Applied Research | 2010年 / 1卷 / 02期
关键词：
Mechanical properties; Reduced activation steels; Structure; Weldability;
D O I：
10.1134/S2075113310020085
中图分类号：
学科分类号：
摘要：
The structure and mechanical properties of candidate materials for nuclear power plants, namely, reduced activation chromium-manganese steels, grade Cr12Mn20W, are investigated, including mechanical properties of weld joints and seams just after the welding process and after additional aging at 400 and 600°C. The investigated steels are characterized by high values of strength properties irrespective of the carbon content. The ultimate strength and yield stress of the weld seam metal are higher than the respective properties of the weld joint. Destruction of nearly all samples arranged with weld joints occurs in the parent metal. Extended holding at the temperature of 400°C for 5000 h actually does not affect the mechanical properties and does not result in a decrease in the material ductility irrespective of the carbon content. Holding at 600°C for over 100 h results in a decrease in elasticity of both the parent metal and the weld joint. Carbides of M23C6 type are evolved in aging, mainly at the grain boundaries. Formation of s-phase was not observed in the aged samples. The tendency of the steels to form hot cracks upon welding is significantly decreased when the carbon content is decreased. The best combination of strength and elasticity, especially at low temperatures, is observed for steel, grade 10Cr12Mn20W. © Pleiades Publishing, Ltd., 2010.
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页码：115 / 124
页数：9
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共 20 条
  • [1] Klueh R.L., Maziasz P.J., Reduced Activation Austenitic Stainless: The Fe-Mn-Cr System, pp. 56-60, (1990)
  • [2] Abe F., Gamer F.A., Kayano H., Effect of carbon on irradiation hardening of reduced-activation 10Cr-30Mn austenic steels, J. Nucl. Mater., 212-215, pp. 761-765, (1994)
  • [3] Ohnuki S., Takahashi H., Kinoshita H., Moshizuki S., Mechanical properties of low-activated Fe-Cr-Mn alloys neutron-irradiated at low temperature, J. Nucl. Matter., 212-215, pp. 755-759, (1994)
  • [4] Ivanov L.I., Platov Y.M., Demina E.V., Trends of chrome-manganese (Cr-Mn) steels application in thermonuclear energetics, Perspekt. Mater., 2, pp. 37-42, (1995)
  • [5] Lyakishev N.P., Prospect of development and manufacturing of low activation metallic materials for fusion reactor, Journal of Nuclear Materials, 233-237, PART II, pp. 1516-1522, (1996)
  • [6] Fedorov V.V., Dyomina E.V., Zasadny T.M., Ivanov L.I., Prusakova M.D., Vinogradova N.A., Zabelin A.M., Hydrogen permeability over the joint weld of the steel parts of fusion reactor with magnet confinement of plasma, J. Nucl. Mater., 307-311, pp. 43-52, (2002)
  • [7] Ivanov L.I., Dyomina E.V., Platov Y.M., Mechanical characteristics and swelling of austenitic Fe-Cr-Mn steels irradiated in the SM-2 and BOR-60 reactors, J. Nucl. Mater., 179-181, pp. 637-639, (1991)
  • [8] Shamardin V.K., Ivanov L.I., Demina E.V., Bulanova T.M., Neustroev V.S., Prusakova M.D., Effect of neutron flows in BOR-60 reactor onto steel cover materials, Fiz. Khim. Obrab. Mater., 6, pp. 5-8, (1989)
  • [9] Vertkov A.V., Evtikhin V.A., Lyublinski I.E., Syichev A.A., Demina E.V., Prusakova M.D., Mechanical properties of low activation Cr-Mn austenitic steels changes in liquid lithium, Journal of Nuclear Materials, 203, 2, pp. 158-163, (1993)
  • [10] Demina E.V., Nechaev A.F., Dokl'nitsyn V.A., Prusakova M.D., Vinogradova N.A., Orlova G.D., Radiation corrosion of austenic chromium-manganese (Cr-Mn) steels in technological environments of nuclear power plants, Perspekt. Mater., Special Issue: Tr. IX Mezhd. Rossiisko-Kitaiskogo Simp., pp. 285-291, (2007)
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