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NSUF 14-505: Investigation of Cr segregation and thermal stability and hardening effects of nanoscale solute clusters and a' precipitates in irradiated Fe-Cr alloys

High chromium ferritic/martensitic (F-M) steels are one of the strong contenders for structural components of the next generation of nuclear reactors and future fusion reactors....

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  • Atom probe datasets from neutron irradiated Fe-Cr alloys

    A series of model Fe–Cr alloys containing 3–18 at.% Cr was neutron irradiated at a nominal temperature of 563 K to 1.82 dpa. Solute distributions were analyzed by atom probe...
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    • The data at this site comes from research conducted through the U. S. Department of Energy’s (DOE) Nuclear Science User Facilities (NSUF) program. The data provided at this site is for information only and is not provided for any particular purpose or use. Neither the U. S. Government nor any agency thereof (including DOE), Battelle Energy Alliance, LLC (BEA), nor any other entity makes any warranties, representations, or guarantees, express or implied, regarding the data provided at this site, including, without limitation, that the data is fit or safe for any use or purpose or that its use would not infringe privately owned rights. Neither the U. S. Government nor any agency thereof (including DOE), BEA, nor any other entity associated with DOE’s NSUF program assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any data on this site. Reference herein, if any, to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not constitute or imply its endorsement, recommendation, or favor by the U. S. Government or any agency thereof (including DOE), BEA, or any other entity.

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