作者: G. Gupta , Z. Jiao , A.N. Ham , J.T. Busby , G.S. Was
DOI: 10.1016/J.JNUCMAT.2006.02.028
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摘要: Abstract Understanding radiation effects in ferritic–martensitic alloys is critical for their success advanced reactor and transmutation systems. The objective of this work to evaluate the microstructural mechanical property changes irradiated alloy T91. Irradiations were conducted with 2.0 MeV protons doses 3, 7, 10 dpa at a dose rate 2 × 10−5 dpa/s temperatures 400 °C, 450 °C, 500 °C. post irradiation microstructure contained high density black-dots a0〈1 0 0〉 dislocation loops addition precipitates tangled dislocations that present unirradiated condition. sensitive heat treatment. Results show did not contain any voids or evidence second phase formation. Hardness increases tends saturate around 5 dpa 400 °C irradiation. Only portion hardening can be accounted by observable features. An initial investigation effect on prior austenite grain boundary microchemistry revealed Cr enriched 4.7 wt%, V 0.6 wt% (nearly 300%), Fe depleted 5.3 wt% relative bulk values. No segregation was observed radiation-induced martensite lath boundaries. Overall, consistent spallation system experiments.