High heat flux testing of 12-14Cr ODS ferritic steels

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.


Published in:
Journal Of Nuclear Materials, 396, 20-25
Year:
2010
Publisher:
Elsevier
ISSN:
0022-3115
Keywords:
Laboratories:
SPC
CRPP




 Record created 2010-05-31, last modified 2018-01-28

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