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High-Temperature Embrittlement of Ferritic and Austenitic Stainless Steels Irradiated up to 1.6 × 1022 n/cm2 (> 0.1 MeV) Pages: 11 Published: Jan 1973
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View License Agreement Source: STP529-EB Abstract Tension specimens of four basic stainless steels having a body-centered cubic (bcc) or face-centered cubic (fcc) structure without or with nickel addition have been fabricated by casting and by powder metallurgy (without and with TiO2 addition). These specimens have been irradiated at 60 C (140 F) up to a 1.6 × 1022 n/cm2 fast fluence (> 0.1 MeV) and ruptured at 700 C (1292 F). A structural and statistical analysis shows that bcc structure, powder metallurgy fabrication methods, TiO2 additions, and transgranular rupture enhance the 700 C resistance to fast neutron embrittlement. The degree of embrittlement is related to the rupture mode before irradiation. Keywords: irradiation, neutron irradiation, radiation effects, tension tests, ductility, elongation, microstructure, embrittlement, grain boundaries, cracking, failure, crystal structure, dispersions, dispersion hardening, powder metallurgy, alloys, ferritic stainless steels, austenitic stainless steels Paper ID: STP35460S Committee/Subcommittee: E10.07 DOI: 10.1520/STP35460S ASTM International is a member of CrossRef. | ||