Repository logo

Infoscience

  • English
  • French
Log In
Logo EPFL, École polytechnique fédérale de Lausanne

Infoscience

  • English
  • French
Log In
  1. Home
  2. Academic and Research Output
  3. Journal articles
  4. Development and characterisation of a new ODS ferritic steel for fusion reactor application
 
Loading...
Thumbnail Image
research article

Development and characterisation of a new ODS ferritic steel for fusion reactor application

Oksiuta, Z.
•
Olier, P.
•
de Carlan, Y.
Show more
2009
Journal Of Nuclear Materials

This paper describes the microstructure, tensile properties and Charpy impact resistance of a reduced activation oxide dispersion strengthened ferritic steel Fe-14Cr-2W-0.3Ti-0.3Y(2)O(3) produced by mechanical alloying of a pre-alloyed, gas atomised steel powder with Y2O3 particles, compaction by hot extrusion at 1100 degrees C, hot rolling at 700 degrees C and heat treatment at 1050 degrees C for 1 h. At room temperature the material exhibits a high ultimate tensile strength of about 1420 MPa and high yield strength of about 1340 MPa in the transverse direction. In the longitudinal direction the values are about 10% lower, due to the anisotropy of the microstructure (elongated grains in the rolling direction). At 750 degrees C the material still exhibits relatively high yield strengths of about 325 MPa and 305 MPa in the longitudinal and transverse directions, respectively. The material exhibits reasonable uniform and total elongation values over the temperature range 23-750 degrees C, in both transverse and longitudinal directions. The material exhibits weak Charpy impact properties in the transverse direction. Charpy impact properties are slightly better in the longitudinal direction, with upper shelf energy of about 4.2 J and a ductile-to-brittle transition temperature of about 8.8 degrees C. (C) 2009 Elsevier B.V. All rights reserved.

  • Details
  • Metrics
Type
research article
DOI
10.1016/j.jnucmat.2009.05.013
Web of Science ID

WOS:000269582700015

Author(s)
Oksiuta, Z.
•
Olier, P.
•
de Carlan, Y.
•
Baluc, N.  
Date Issued

2009

Publisher

Elsevier

Published in
Journal Of Nuclear Materials
Volume

393

Start page

114

End page

119

Subjects

Tensile

•

Alloys

Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
CRPP  
SPC  
Available on Infoscience
November 30, 2010
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/59897
Logo EPFL, École polytechnique fédérale de Lausanne
  • Contact
  • infoscience@epfl.ch

  • Follow us on Facebook
  • Follow us on Instagram
  • Follow us on LinkedIn
  • Follow us on X
  • Follow us on Youtube
AccessibilityLegal noticePrivacy policyCookie settingsEnd User AgreementGet helpFeedback

Infoscience is a service managed and provided by the Library and IT Services of EPFL. © EPFL, tous droits réservés