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. Conferences, Workshops, Symposiums, and Seminars
  4. Recent progress toward development of reduced activation ferritic/martensitic steels for fusion applications
 
conference paper

Recent progress toward development of reduced activation ferritic/martensitic steels for fusion applications

Kurtz, R. J.
•
Alamo, A.
•
Lucon, E.
Show more
2009
Journal of Nuclear Materials, Proceedings of the 13th International Conference on Fusion Reactor Materials
13th International Conference on Fusion Reactor Materials

Significant progress has been achieved in the international research effort on reduced activation ferritic/martensitic steels for fusion structural applications. Because this class of steels is the leading structural material for test blankets in ITER and future fusion power systems, the range of ongoing research activities is extremely broad. Since, it is not possible to discuss all relevant work in this brief review, the objective of this paper is to highlight significant issues that have received recent attention. These include: (1) efforts to measure and understand radiation-induced hardening and embrittlement at temperatures <400 °C, (2) experiments and modeling to characterize the effects of He on microstructural evolution and mechanical properties, (3) exploration of approaches for increasing the high-temperature (>550 °C) creep resistance by introduction of a high-density of nanometer scale dispersoids or precipitates in the microstructure, (4) progress toward structural design criteria to account for loading conditions involving both creep and fatigue, and (5) development of nondestructive examination methods for flaw detection and evaluation.

  • Details
  • Metrics
Type
conference paper
DOI
10.1016/j.jnucmat.2008.12.323
Web of Science ID

WOS:000266386900103

Author(s)
Kurtz, R. J.
Alamo, A.
Lucon, E.
Huang, Q.
Jitsukawa, S.
Kimura, A.
Klueh, R. L.
Odette, G. R.
Petersen, C.
Sokolov, M. A.
Show more
Date Issued

2009

Publisher

Elsevier

Publisher place

The Netherlands

Published in
Journal of Nuclear Materials, Proceedings of the 13th International Conference on Fusion Reactor Materials
Volume

386-388

Start page

411

End page

417

Subjects

Fatigue-Oxidation Interactions

•

Containing Martensitic Steels

•

Mechanical-Properties

•

Holding Period

•

Vacuum Vessel

•

Helium

•

Irradiation

•

Creep

•

Components

•

Iter

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
CRPP  
SPC  
Event nameEvent placeEvent date
13th International Conference on Fusion Reactor Materials

Nice, France

December 10-14, 2007

Available on Infoscience
April 9, 2010
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/49291
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