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Garner, F.A.; Toloczko, M.B.; Eiholzer, C.R.
Fusion reactor materials semiannual progress report for the period ending March 31, 19931993
Fusion reactor materials semiannual progress report for the period ending March 31, 19931993
AbstractAbstract
[en] The irradiation creep behavior of the fusion heats of HT9 and 9Cr-1Mo at ∼400 degrees C has been measured to exposures as large as 208 dpa. HT9 is somewhat 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 strain data of both alloys appear to include some contributions from precipitate-related density changes. Swelling may have occurred in 9Cr-1Mo
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Oak Ridge National Lab., TN (United States); 524 p; Jul 1993; p. 171-173; Also available from OSTI as DE94006108; NTIS
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Progress Report
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