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A REVIEW ON CURRENT STATUS OF ALLOYS 617 AND 230 FOR GEN IV NUCLEAR REACTOR INTERNALS AND HEAT EXCHANGERS...

by Weiju Ren, Robert W Swindeman
Publication Type
Journal
Journal Name
Journal of Pressure Vessel Technology
Publication Date
Volume
131
Issue
4

Alloys 617 and 230 are currently identified as two leading candidate metallic materials in the down selection for applications at temperatures above 760�C in the Gen IV Nuclear Reactor Systems. Qualifying the materials requires significant information related to Codification, mechanical behavior modeling, metallurgical stability, environmental resistance, and many other aspects. In the present paper, material requirements for the Gen IV Nuclear Reactor Systems are discussed; certain available information regarding the two alloys under consideration for the intended applications are reviewed and analyzed. Suggestions are presented for further R&D activities for the materials selection.