Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 386-88, Issue -, Pages 525-528Publisher
ELSEVIER
DOI: 10.1016/j.jnucmat.2008.12.167
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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 similar to 550 degrees C to about 650 degrees C. Temperatures above 700 degrees 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-0.3Y(2)O(3) ferritic ODS steel is being developed, using an Attritor with varying milling parameters. Afterwards the mechanically alloyed powders were encapsulated, scaled 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. (C) 2008 Elsevier B.V. All rights reserved.
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