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- W2019932756 abstract "Abstract New experimental steels were designed and tested as the reduced activation alternatives to the current austenitic and ferritic prime candidate alloys for applications to the first wall structural components of Tokamak reactors. The design was based on the experience and the knowledge implemented in the recent nuclear and non-nuclear material fields, in which optimization was attempted on the basic properties, keeping their levels equivalent to or better than those of the conventional candidates. Four proto-type alloys were melted for testing with the following compositional specifications: 0.1 C-8 Cr-2 W-0.2 V-Fe, 0.1 C-8 Cr-2 W-0.2 V-0.04 Ta-Fe, 0.25 C-25 Mn-14 Cr-0.2 Ti-Fe and 0.02 C-18 Ni-18 Cr-0.3 Ti-Fe. In the first phase of the evaluation program, tests were made to determine properties that included tensile, creep-rupture, impact before and after thermal aging, wet and dry corrosion, and weldability properties. These results are compaed with those of the conventionally known materials of the equivalent classes. Among the materials tested the ferritic alloy with 0.04 Ta showed particularly attractive features." @default.
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- W2019932756 date "1986-11-01" @default.
- W2019932756 modified "2023-10-02" @default.
- W2019932756 title "Development of potential low activation ferritic and austenitic steels" @default.
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- W2019932756 doi "https://doi.org/10.1016/0022-3115(86)90144-3" @default.
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