N. A. Artemov

Institute for Physics and Power Engineering A.I. Leypunsky, Obninsk, Kaluga, Russia

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Publications (5)4.41 Total impact

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    ABSTRACT: The effect of alloying and fast-neutron irradiation on the behavior of interstitial impurities in vanadium and V-Ga and V-Ti-Cr alloys is studied using low-frequency internal friction. It is found that, before irradiation, oxygen and nitrogen impurities in plain vanadium and V-Ga alloys are in a solid solution, whereas, in V-Ti and V-Ti-Cr alloys, they are predominantly fixed to form chemical compounds. Unlike the irradiation of plain vanadium, the irradiation of V-Ga alloys at 673 K to a neutron fluence of 4.24 × 1025 m−2 (E > 0.1 MeV) does not knock out oxygen and nitrogen impurities from interstitial positions in the lattice to the positions of radiation defects. In the V-5Ti-5Cr alloy, oxygen and nitrogen atoms are fixed before and after neutron irradiation according to these conditions.
    Russian Metallurgy (Metally) 05/2008; 2008(3):239-244.
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    ABSTRACT: The effects of neutron irradiation and annealing on the elastic moduli and electrical resistivity of Mo and W were studied using single-crystal samples oriented with their axis along [100], [110], and [111]. The samples were irradiated with fast neutrons (E> 0.1 MeV) to a neutron fluence of 1.14 1026n/m2in a BR-10 reactor at 460C. The irradiation-induced changes in resistivity and elastic moduli were found to be orientation-dependent. Irradiated W was found to exhibit elastic anisotropy and relaxation of the shear and Young's moduli. Isochronal annealing below 0.7t mdid not reduce the resistivity of the samples to its initial level, presumably because of the formation of radionuclides, while the shear and Young's moduli were restored to their initial levels.
    Inorganic Materials 07/2001; 37(8):786-789. · 0.38 Impact Factor
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    ABSTRACT: Vanadium and vanadium alloys with gallium, chromium and cerium were irradiated at 400°C in the BR-10 reactor. The neutron fluence was 5.15·1025 n/m2 (E>0.1 MeV). The elastic modules (E and G) and swelling of the alloys were measured after irradiation. It is established that swelling in the alloys is negligible and the elastic properties do not change significantly after irradiation. The experimental results are briefly discussed.
    Journal of Nuclear Materials 01/1998; 258:1409-1413. · 2.02 Impact Factor
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    ABSTRACT: Results of the experimental study of some physical, mechanical and technological properties of the reduced activation vanadium—gallium-based alloys are presented. The activation calculations show that Ga has the lowest cooling time not only in comparison with alloying elements Ti and Cr in low activation VTiCr alloys but also with vanadium. The effect of Ga(1–8 at%), Cr (5–6 at%) and Ce(0.05–0.1 at%) on workability, mechanical properties, thermal conductivity, elastic modulus (E,G), and Poisson's ratio of VGa was studied. The same properties of some are also studied. The level of tensile properties, thermal conductivity and elastic properties of VGa alloys are comparable with VTiCr alloys, but their activation parameters and ductility are superior. The experimental results make it possible to recommend VGa-based alloys as reduced activation structure materials for fusion reactors.
    Journal of Nuclear Materials 01/1996; 233:395-399. · 2.02 Impact Factor
  • M. I. Zakharova, N. A. Artemov, D. V. Petrov
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    ABSTRACT: The temperature dependencies of elastic modulus, internal friction, Poisson ratio in the range from 20 to 600°C as well as of thermal conductivity and electrical resistance at temperatures from 20 to 1000°C have been determined for type 13Cr2MoNbVB ferritic—martensitic steel irradiated at 280°C in the BN-350 fast reactor to neutron fluence of 4.03 × 1026 n/m2 (E > 0.1 MeV). During isochronal annealings at temperatures up to 0.65Tm the recovery of the properties for irradiated steel has been investigated in the range of homologous temperatures from 0.28Tm to 0.53Tm. A pronounce recovery was observed at four substages in the temperature interval from 380 to 620°C. The activation energies determined for all recovery substages varied from 1.11 eV to 4.09 eV.
    Journal of Nuclear Materials - J NUCL MATER. 01/1996; 233:280-284.