ACTIVATION AND RADIATION DAMAGE BEHAVIOUR OF RUSSIAN STRUCTURAL MATERIALS IN THE FISSION AND FUSION REACTORS

Authors & Affiliations

Blokhin A.I.1, Chernov V.M.2, Demin N.A.2
1A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2A.A.Bochvar High-tech Research Institute of Inorganic Materials, Moscow, Russia

Abstract

Various structural low activated materials have been proposed as a candidate for the first walls-blankets of fusion reactors. One of the main problems connected with using these materials - to minimise the production of long-lived radionuclides from nuclear transmutations and to provide with good technological and functional properties. The selection of materials and their metallurgical and fabrication technologies for fusion reactor components is influenced by this factor. Low activated V-Ti-Cr alloys and low activated ferritic-martensitic steels with 9- 12% Cr are a leading candidate material for fusion first wall and blanket applications. Materials “were irradiated” by fission (BN-600, BOR-60) and fusion (Russian DEMO-RF Reactor Project) typical neutron spectra with neutron fluency up to 1022 n/cm2 and the cooling time up to 1000 years. For these materials manufactured in Russia (Russia technologies) the analysis of induced activity, hydrogen and helium production as well as the accumulation of such elements as C, N, O, P, S, Zn and Sn as a function of irradiation time was performed.

Keywords
construction materials, fusion reactor, elemental composition, austenitic, ferritic steels, material transmutations, ferritic-martensitic steels, V-Ti-Cr alloys, accumulation of radioactive and stable products

Article Text (in Russian, PDF)

References

UDC 621.039

Problems of Atomic Science and Technology. Series: Nuclear Constants, issue 1-2, 2005