Chemical segregation behavior of the low activation ferritic/martensitic steel F82H

The microstructure of the low activation F82H ferritic/martensitic steel has been investigated in the case of the heat treated and irradiated material. The irradiation has been achieved with 590 MeV protons in the PIREX facility to a dose of 0.5 dpa at a temperature of 523 K. The mechanical properties being intrinsically related to the chemistry of the metal, the understanding of the segregation behavior of the different alloying elements to microstructure defects, such as boundaries, is crucial. The segregation behavior to irradiation of both martensite laths and pre-austenite grain (PAG) boundaries is investigated using energy filtered transmission electron microscopy (EFTEM). It appears that Fe depletion of boundaries is observed in all cases, and the heat treated material experiences Cr segregation to boundaries, while the irradiated material experiences Cr depletion. (C) 1998 Elsevier Science B.V. All rights reserved.


Published in:
Journal of Nuclear Materials, 258-263, 1350-1355
Year:
1998
ISSN:
0022-3115
Note:
8th International Conference on Fusion Reactor Materials (ICFRM-8) OCT 26-31, 1997 SENDAI, JAPAN B
Laboratories:
SPC
CRPP




 Record created 2008-04-16, last modified 2018-01-28


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