Microstructural development in low activation ferritic alloys irradiated to 200 dpa at 420{degree}C [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy, 1993.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: 11 pages : digital, PDF file
Additional Creators:: Pacific Northwest Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

Density change and microstructural development are reported for nine low activation ferritic steels covering the range 2.3 to 12 Cr with varying additions of V and/or W for hardening and up to 6.5 Mn for austenite stability. Specimens were examined following irradiation in FFTF/MOTA at 4200°C to a dose exceeding 200 dpa. Void swelling was found, but the swelling remained at 5% or below, with the worst case in an alloy of 9Cr-2Mn-1WV. The carbide structure pinning Martensite lath boundaries remains in place.

Report Numbers:

E 1.99:pnl-sa--22526
E 1.99: conf-930928--21
conf-930928--21
pnl-sa--22526

Subject(s):

Materials Science

Other Subject(s):

Note:

Published through SciTech Connect.
12/01/1993.
"pnl-sa--22526"
" conf-930928--21"
"DE94004269"
6. international conference on fusion reactor materials,Stresa (Italy),27 Sep - 1 Oct 1993.
Gelles, D.S.

Funding Information:

AC06-76RL01830

View MARC record | catkey: 14456022