Irradiation creep and swelling of the U.S. fusion heats of HT9 and 9Cr-1Mo to 208 dpa at {approximately}400{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:
- 12 pages : digital, PDF file
- Additional Creators:
- Pacific Northwest Laboratory
United States. Department of Energy
United States. Department of Energy. Office of Scientific and Technical Information - Access Online:
- www.osti.gov
- Summary:
- Ferritic-martensite steels are being considered for structural applications in fusion reactors. In order to provide data on the response of such steels to radiation, a series of experiments have been conducted in FFTF. Here, the irradiation creep and swelling behaviors of the fusion heats of HT9 and 9Cr-1Mo at ∼400 C have been measured to exposures as large as 208 dpa, using both diametral and density measurements of helium-pressurized creep tubes. Void swelling was found in both alloys at 208 dpa to occur at rates of 0.012%/dpa or less, with the swelling of HT9 exhibiting a larger degree of stress enhancement than 9Cr-1Mo. The creep rate of HT9 is rather nonlinear in its response to hoop stress level in the range 0--200 MPa, but 9Cr-1Mo exhibits only slightly greater than linear behavior with stress level. The creep-swelling coupling coefficients for 9Cr-1Mo are consistent with values obtained for other steels.
- Subject(s):
- Note:
- Published through SciTech Connect.
09/01/1993.
"pnl-sa--22442"
" conf-930928--17"
"DE94004367"
6. international conference on fusion reactor materials,Stresa (Italy),27 Sep - 1 Oct 1993.
Garner, F.A.; Eiholzer, C.R.; Toloczko, M.B. - Funding Information:
- AC06-76RL01830
View MARC record | catkey: 14745676