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(FTP1/07(R)) Reduced Activation Ferritic Steel R&D in US/Japan Collaborative Research

A. K. Kimura1), A. Kohyama1), K. Shiba2), R. L. Klueh3), D. S. Gelles4), G. R. Odette5)
 
1) Institute of Advanced Energy, Kyoto University, Uji, Kyoto, Japan
2) Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki, Japan
3) Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA
4) Pacific Northwest National Laboratory, Richland, Washington, USA
5) University of California, Santa Barbara, California, USA

Abstract.  Material performance of reduced activation ferritic steels (RAFS) and their response to neutron irradiation, which have been investigated by utilizing fission reactors under the US/Japan collaborative research program (JUPITER), are summarized. Rather high resistance to neutron irradiation and helium was recognized for 9Cr-2W RAFS; irradiation hardening and helium embrittlement of RAFS were evaluated to be much less than for other candidate materials. Alloy design of high-temperature steels and the development of oxide dispersion-strengthened steels have been progressing.

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IAEA 2001