High heat flux testing of 12–14Cr ODS ferritic steels
Source abstract
Abstract
The thermal performance of Fe-(12-14)Cr-2W-0.3Ti-0.3Y(2)O(3) ODS reduced activation ferritic steels, which are considered as candidate first wall materials for the future fusion power reactors and were manufactured by mechanical alloying in hydrogen and hot isostatic pressing, was assessed by high heat flux (HHF) testing with the electron beam JUDITH facility at the Forschungszentrum Julich (FZJ), Germany. An analysis of the microhardness and microstructure of the specimens was done before and after HHF tests.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · High-Temperature Coating Behaviors
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References (11)
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