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Volumn 392, Issue 3, 2009, Pages 379-385
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Evaluation of alloy 690 process pot at the contact with borosilicate melt pool during vitrification of high-level nuclear waste
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Author keywords
[No Author keywords available]
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Indexed keywords
ALLOY 690;
AUSTENITIC MATRIX;
BOROSILICATE MELTS;
COMPOSITIONAL MODIFICATION;
CR CARBIDE;
CR DEPLETION;
EXPERIMENTAL STUDIES;
HIGH-LEVEL NUCLEAR WASTES;
INTERGRANULAR ATTACK;
LIFE SPAN;
MATERIAL BEHAVIOUR;
SERVICE CONDITIONS;
TIME PERIODS;
VITRIFICATION PROCESS;
ALLOYS;
CARBIDES;
CHROMIUM;
GRAIN BOUNDARIES;
LAKES;
RADIATION DAMAGE;
RADIOACTIVE WASTES;
VITRIFICATION;
PRECIPITATION (CHEMICAL);
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EID: 67650998512
PISSN: 00223115
EISSN: None
Source Type: Journal
DOI: 10.1016/j.jnucmat.2008.07.046 Document Type: Article |
Times cited : (36)
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References (15)
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