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Zinkle, S.J.; Garner, F.A.; Barabash, V.R.; Fabritsiev, S.A.; Pokrovsky, A.S.
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] A total of 74 alloys of varying composition and thermomechanical condition have been prepared for a joint US-Russia irradiation experiment in the SM-3 reactor in Dimitrovgrad, Russia. The alloys will be irradiated in the form of TEM disks and sheet tensile specimens at temperatures of about 120, 250, and 340 degrees C for one 45-day cycle in the core and Channel 2 irradiation positions. This will produce damage levels of about 7 and 1 dpa, respectively. Cadmium shielding will be used in the Channel 2 position to shield the thermal neutrons and thereby reduce the amount of solid transmutation products in copper
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Oak Ridge National Lab., TN (United States); 524 p; Jul 1993; p. 347-351; Also available from OSTI as DE94006108; NTIS
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Report
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Progress Report
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