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Microstructural stability of tantalum-alloyed ferritic-martensitic steel with neutron irradiation to 7.4 dpa at ~490 °C

Journal Article · · Materialia

Specimens of a reduced-activation ferritic-martensitic steel, called CNA1, were irradiated to 7.4 displacements per atom at ~490 °C in the High Flux Isotope Reactor. Vickers hardness and tensile properties revealed consistent softening that is attributed to some recovery during irradiation, with reduced laths and dislocation density. Detailed microstructural characterization by transmission electron microscopy and energy dispersive x-ray spectroscopy showed radiation-induced dislocation loops, few cavities, and slight dissolution of M23C6 and MX precipitates. Partial amorphization was only observed in M23C6 precipitated in matrix. Transmutation somewhat destabilized M23C6 and MX, with a stronger effect on the later one by noticeable depletion of Ta with enriched W, which is consistent with the transmutation calculations. The microstructural evolution and associated strength changes were discussed with the assistance of computational thermodynamics.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1606978
Alternate ID(s):
OSTI ID: 1599266
Journal Information:
Materialia, Journal Name: Materialia Journal Issue: C Vol. 9; ISSN 2589-1529
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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  • Campbell, Anne A.; Porter, Wallace D.; Katoh, Yutai
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 370 https://doi.org/10.1016/j.nimb.2016.01.005
journal March 2016
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