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Evaluation of Ferritic Alloy Fe-2¼Cr-1Mo After Neutron Irradiation: Microstructural Development Pages: 28 Published: Jan 1987
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View License Agreement Source: STP955-EB Abstract As part of a program to provide a data base on the bainitic alloy Fe-2¼Cr-1Mo for fusion energy applications, microstructural examinations are reported for nine specimen conditions for 2¼Cr-1Mo steel that had been irradiated by fast neutrons over the temperature range 390 to 510°C. Void swelling is found following irradiation at 400 to 480°C. Concurrently dislocation structure and precipitation developed. Peak void swelling, void density, dislocation density, and precipitate number density formed at the lowest temperature, approximately 400°C, whereas mean void size and mean precipitate size increased with increasing irradiation temperature. The examination results are used to provide interpretation of in-reactor creep, density change, and post irradiation tensile behavior. Keywords: neutron irradiation, alloys, swelling, ferritic alloys Paper ID: STP33844S Committee/Subcommittee: E10.07 DOI: 10.1520/STP33844S ASTM International is a member of CrossRef. | ||