Microstructural evolution of NF709 (20Cr–25Ni–1.5MoNbTiN) under neutron irradiation [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy, 2015.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy
Physical Description:: pages 229-235 : digital, PDF file
Additional Creators:: Oak Ridge National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

In this study, because of its superior creep and corrosion resistance as compared with general austenitic stainless steels, NF709 has emerged as a candidate structural material for advanced nuclear reactors. To obtain fundamental information about the radiation resistance of this material, this study examined the microstructural evolution of NF709 subjected to neutron irradiation to 3 displacements per atom at 500 °C. Transmission electron microscopy, scanning electron microscopy, and high-energy x-ray diffraction were employed to characterize radiation-induced segregation, Frank loops, voids, as well as the formation and reduction of precipitates. Radiation hardening of ~76% was estimated by nanoindentation, approximately consistent with the calculation according to the dispersed barrier-hardening model, suggesting Frank loops as the primary hardening source.

Report Numbers:

E 1.99:1234352

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Note:

Published through SciTech Connect.
12/30/2015.
Journal of Nuclear Materials 470 C ISSN 0022-3115 AM
Kim, Byoungkoo [ORNL]; Tan, Lizhen [ORNL]; Xu, C.; Yang, Yong [University of Florida, Gainesville]; Zhang, Xuan [Argonne National Laboratory (ANL)]; Li, Meimei [Argonne National Laboratory (ANL)].

Funding Information:

AC05-00OR22725

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