Title of article
Characteristic results and prospects of the 13Cr–1W–0.3Ti–0.3Y2O3 ODS steel
Author/Authors
Eiselt، نويسنده , , Ch.Ch. and Klimenkov، نويسنده , , M. and Lindau، نويسنده , , R. and Mِslang، نويسنده , , A.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2009
Pages
4
From page
525
To page
528
Abstract
For specific blanket and divertor applications in future fusion power reactors a replacement of presently considered reduced activation ferritic martensitic (RAFM) steels as structural material by suitable oxide dispersion strengthened (ODS) ferritic martensitic steels would allow a substantial increase of the operating temperature from ∼550 °C to about 650 °C. Temperatures above 700 °C in the He cooled modular divertor concept necessitates the use of ferritic (RAF) ODS steels, which are not limited by a phase transition. Therefore a 13Cr–1W–0.3Ti–0.3Y2O3 ferritic ODS steel is being developed, using an Attritor with varying milling parameters. Afterwards the mechanically alloyed powders were encapsulated, sealed and consolidated in a hot isostatic press device. In this work, the effects of several parameter variations on the microstructure of the produced ferritic ODS-alloys, analysed by optical microscopy (OM) and high resolution TEM, as well as results of conducted mechanical tests are presented.
Journal title
Journal of Nuclear Materials
Serial Year
2009
Journal title
Journal of Nuclear Materials
Record number
1366279
Link To Document