Abstract
A reduced activation ferritic steel, 8Cr2W0.2V0.04TaFe, is one of the candidates for the first wall material of SSTR (Steady State Tokamak Reactor). There is a growing demand for extensive properties data for designing the structure of the first wall. In a program of expanding of the data base, tensile tests at room, and elevated temperatures, creep rupture tests, Charpy impact tests and measurements of the physical properties were performed on the mill production plates as well as some laboratory heats. Some of the tests were conducted on specimens that were thermally aged up to 36Ms. Recent data were summarized and compared with those for the well known ferritic steels, HT9 and modified 9Cr.
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