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

Abstract 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.

[1]  H. Matsui,et al.  Designation of alloy composition of reduced-activation martensitic steel , 1994 .

[2]  K. Nishimura,et al.  Exchange and reduction of retained hydrogen isotope by glow discharges , 2011 .

[3]  S. Ohnuki,et al.  Formation of nanoscale complex oxide particles in mechanically alloyed ferritic steel , 2004 .

[4]  Shigeru Takaya,et al.  Corrosion resistance of Al-alloying high Cr–ODS steels in stagnant lead–bismuth , 2010 .

[5]  M. Mathon,et al.  Assessment of ODS-14%Cr ferritic alloy for high temperature applications , 2004 .

[6]  H. Ullmaier,et al.  The mechanical properties of an Alloy 718 window after irradiation in a spallation environment , 2001 .

[7]  J. Lee,et al.  Influence of alloy composition and temperature on corrosion behavior of ODS ferritic steels , 2011 .

[8]  T. Fujisawa,et al.  Effects of extrusion temperature on the nano-mesoscopic structure and mechanical properties of an Al-alloyed high-Cr ODS ferritic steel , 2011 .

[9]  G. Benamati,et al.  Mechanical and corrosion behaviour of EUROFER 97 steel exposed to Pb–17Li , 2002 .

[10]  P. Fauvet,et al.  Corrosion of austenitic and martensitic stainless steels in flowing 17Li83Pb alloy , 1988 .

[11]  G. R. Odette,et al.  The development and stability of Y–Ti–O nanoclusters in mechanically alloyed Fe–Cr based ferritic alloys , 2004 .

[12]  A. Kimura,et al.  Corrosion properties of oxide dispersion strengthened steels in super-critical water environment , 2004 .

[13]  A. Kimura,et al.  Development of Fuel Clad Materials for High Burn-up Operation of LWR , 2005 .

[14]  H. Kolbe,et al.  Effects of Pb17Li on the tensile properties of steels , 1988 .

[15]  H. Borgstedt,et al.  Corrosion testing of steel X 18 CrMoVNb 12 1 (1.4914) in A Pb17Li pumped loop , 1988 .

[16]  T. Okuda,et al.  Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I) , 2012 .

[17]  Todd R. Allen,et al.  The effects of low dose rate irradiation and thermal aging on reactor structural alloys , 1999 .

[18]  T. Sample,et al.  Liquid metal embrittlement (LME) susceptibility of the 8?9% Cr martensitic steels F82H-mod., OPTIFER IVb and their simulated welded structures in liquid Pb?17Li , 2000 .