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AbstractAbstract
[en] The purpose of this work was to determine whether the impact behavior of irradiated V-15Cr-5Ti could be improved by removing the hydrogen which is suspected to be contributing to the radiation-induced degradation previously observed in the ductile to brittle transition temperature (DBTT)
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Jun 1989; 4 p; CONTRACT AC06-76RL01830; W-31109-ENG-38; NTIS, PC A02/MF A01 as DE90015289; OSTI; INIS; US Govt. Printing Office Dep; To be submitted for publication as part of the Fusion Reactor Materials semiannual progress report, March 31, 1989.
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