Published October 1, 2011 | Version v1
Journal article

Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems

  • 1. Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)
  • 2. Kobelco Research Institute, Inc., Takatsukadai 1-5-5, Nishi-ku, Kobe 651-2271 (Japan)
  • 3. Advanced Nuclear System R and D Directorate, Japan Atomic Energy Agency, Narita 4002, Oarai, Higashi-ibaraki, Ibaraki 311-1393 (Japan)
  • 4. Graduate School of Engineering, Hokkaido University, N13, W8, Kita-ku, Sapporo 060-8628 (Japan)
  • 5. EcoTopia Science Institute, Nagoya University, Furo, Chikusa-ku, Nagoya 464-8603 (Japan)
  • 6. Structural Metals Center, National Institute for Materials Science, Sengen 1-2-1, Tsukuba, Ibaraki 305-0047 (Japan)

Description

A successful example of high-Cr oxide dispersion strengthened (ODS) steels development is introduced with showing key technologies to overcome the issues to meet material requirements for next generation nuclear systems as well as fusion blanket systems. Corrosion issue requires Cr concentration more than 14 wt.%, but aging embrittlement issue requires it less than 16 wt.%. An addition of 4 wt.%Al is effective to improve corrosion resistance of 16 wt.%Cr-ODS steel in supercritical water (SCW) and lead-bismuth eutectics (LBE), while it is detrimental to high-temperature strength. An addition of small amount of Zr or Hf results in a significant increase in creep strength at 973 K in Al-added ODS steels. Feasibility of high-Cr ODS steel without Al addition is assessed for fusion application in terms of corrosion resistance in SCW.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2010.12.300

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2010.12.300;
PII
S0022-3115(10)01147-5;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
417
Journal Issue
1-3
Journal Page Range
p. 176-179
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
14. international conference on fusion reactor materials
Acronym
ICFRM-14
Dates
7-12 Sep 2009
Place
Sapporo (Japan)

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.