Studying of influence of a neutron irradiation on element contents and structures of aluminum alloys SAV-1 and AMG-2

It is one of fundamental problems in the sphere of the study of construction materials for nuclear reactors to create a radiation-resistant material fit for long-term operation under highdose neutron radiation conditions. At present, SAV-1 and AMG-2 aluminum alloys are used at the WWR-M reactors as fuel elements which differ from other alloys with their physical and mechanical properties, specifically, super-durability, corrosion resistance and high reserve of creepage. This work is devoted to a study into the influence of neutron radiation on the elemental composition and structure of the SAV-1 and AMG-2 alloys. With this aim in view the samples of these alloys were exposed to neutron flux at the WWR-SM reactor at the Institute of Nuclear of Physics of the AS of the RUz, using the fluencies of ≈1019 neutron/sm2. Measurement of neutron flux spectrum Monitors Au, Co, Ni, Ti, Fe have been made from thin roll flat metal foil, and Y and Mg were taken in the form of their connections MgO and Y2O3. Two sets of monitors have been weighed, packed into polyethylene packages, wrapped in aluminum foil and soldered in quartz ampoules. One of ampoules has been soldered in Cd glass for cut-off by component thermal flux in the course of irradiation of monitors. Irradiation of both containers was carried out consistently in the current of 2 hours in the second channel of the reactor general neutrons flux. Measurement of samples’ gamma activity was carried out in 3-10 days after irradiation. Registration of samples gamma spectrum was carried out on HP Ge detector with multichannel analyzer DSA1000 of Canberra firm, processing of gamma spectrum was carried out by means of standard software package Genie 2000. Table 1. Description of monitors % Еп, MeV T1/2 Е, KeV M,mg 197Au(n,γ)198Au 100 2.7d 5 58Ni(n,p)58Co 67,88 2,6 71,3d 810,8(99) 12,25 24Mg(n,p)24Na 78,7 6,3 15,05h 1368,5(100) 1.1457 48Ti(n,p)48Sc 73,94 7 1,83d 1312,1(100) 1037,4(100) 983,5(100) 15.15