Thermal-creep strain of a nuclear fusion reactor first-wall ferrous material modified 9Cr-1Mo steel

Abstract

Experimental thermal-creep strain data for modified 9Cr1Mo steel have been analyzed using an number of empirical relations. Using the results obtained, estimates of the creep deformation of the structural components of the first-wall of a nuclear fusion reactor have been obtained.

Publication Title

American Society of Mechanical Engineers, Materials Division (Publication) MD

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