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A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems...

by Weiju Ren, Robert W Swindeman
Publication Type
Conference Paper
Publication Date
Page Numbers
821 to 836
Conference Name
ASME 2010 Pressure Vessels & Piping Division / K-PVP Conference
Conference Location
Bellevue, Washington, United States of America
Conference Date
-

Alloy 800H is currently under consideration for applications in the Next Generation Nuclear Plant at operational temperatures above 750°C. To provide supporting information in this paper at the attempt to facilitate the consideration, service requirements of the nuclear system for structural materials is first described; and then an extensive review of Alloy 800H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application; an finally further research and development activities to support the materials qualification are suggested.