Thermal deformation behavior of Ti-5Al-3V-3Zr-0.7Cr alloy for pressure housing of reactor

Due to its low density, high melting point, non-magnetic properties, good corrosion resistance and high temperature mechanical properties, titanium alloy has become a candidate material for cladding and structural components in reactors and nuclear fusion reactors, and has attracted more and more researchers' attention. The main problem of its application in nuclear reactors is the influence of hydrogen embrittlement and irradiation caused by hydrogen nuclei generated by nuclear transmutation on the mechanical properties of alloy materials. Because of its minimum expansion rate and better resistance to irradiation embrittlement, titanium alloys near type have become one of the hot spots in the research of nuclear titanium alloys. Russia, the United States, Japan and other developed countries have developed the related reactor near alpha titanium alloy material. Studied the irradiation behavior of titanium alloy and found that the incubation period of Ti-20Zr alloy near type titanium alloy was significantly higher than Ti-5Al-2.5V alloy. When studied the tensile and fatigue properties of titanium alloy used in fusion reactor, they found that the fatigue properties of Ti-5Al-2.4 Sn alloy were significantly better than Ti-6Al-4V used previously. Studied the interface reaction between TA10 alloy and 304 stainless steel, they found that the complexes of TA10 alloy and 304 stainless steel had higher fusion property than the same alloy. However ordinary alpha titanium alloy or difficult to meet the nuclear reactor strength and thermal stability of shell component higher request, therefore Russia first designed the Ti-Al-V-Zr is close to alpha titanium alloy used for the integration of nuclear reactor shell, the Jane form a diameter of 2750 ~ 3500mm, the minimum length of 480 mm, maximum length is 1600 mm, and also use the sheet thickness is 160 mm. Other studies have shown that, according to the calculation results of residual radioactivity, when titanium contains both vanadium and chromium, the near-titanium alloy material will have the maximum decay rate of radiation dose. Obviously, Ti-Al-V-Cr series is more suitable for nuclear reactor structural components. For the newly designed alloy, the selection of deformation temperature and strain rate is very important among the thermal deformation parameters. To study the rheological behavior of the alloy at different temperatures and strain rates is of great significance for mastering its rheological characteristics at high temperature, obtaining reasonable thermal processing parameters and promoting the application of the new alloy.