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Hamilton, M.L.; Huang, F.H.
Pacific Northwest Lab., Richland, WA (USA)1989
Pacific Northwest Lab., Richland, WA (USA)1989
AbstractAbstract
[en] Fracture toughness tests were performed on a number of heats of both HT9 and modified 9Cr-1Mo irradiated in the Fast Flux Test Facility (FFTF) to doses ranging from 35 to over 100 dpa at temperatures of 400 to 600 degrees C. Virtually no additional degradation was observed in either toughness or tearing modulus beyond that observed in the Experimental Breeder Reactor II (EBR-II) at 15 dpa. The FFTF data base for these alloys is compared to that of similar specimens irradiated in the High Flux Isotope Reactor (HFIR) and EBR-II. 6 refs., 5 figs., 2 tabs
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1989; 15 p; 4. international conference on fusion reactor materials; Kyoto (Japan); 4-8 Dec 1989; CONF-891204--10; CONTRACT AC06-76RL01830; NTIS, PC A03/MF A01 as DE90004519; OSTI; INIS; US Govt. Printing Office Dep
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