Compositional and temperature dependence of void swelling in model Fe–Cr base alloys irradiated in the EBR-II fast reactor
TL;DR: In this article, a series of annealed and aged Fe-x Cr, Fe-12Cr, Fe12Cr- y C and Fe-0.1C-z Mo model alloys were irradiated in EBR-II at eight temperatures between 400°C and 650°C with dose levels ranging from 35 to 131 dpa.
About: This article is published in Journal of Nuclear Materials.The article was published on 2000-12-01. It has received 52 citations till now. The article focuses on the topics: Swelling.
Citations
More filters
TL;DR: In this article, the authors simulated displacement cascades up to 50 keV in Fe-10%Cr by molecular dynamics using an embedded-atom method (EAM) interatomic potential which satisfactorily reproduces the interact...
104 citations
TL;DR: In this paper, the effects of rastered and defocused beams, using 3.5 MeV iron ions to irradiate pure iron at 450°C to peak doses of 50 and 150 dpa, were addressed.
81 citations
TL;DR: In this paper, the radiation-induced microstructure of an HT9 ferritic/martensitic hexagonal duct was examined following a six-year irradiation of a fuel assembly in the Fast Flux Test Reactor Facility (FFTF).
76 citations
TL;DR: A dual-phase 12Cr oxide-dispersion-strengthened (ODS) alloy with improved corrosion and oxidation resistance exhibits promising void swelling resistance and microstructural stability under Fe2+ ion irradiation to 800-dpa at 475°C as discussed by the authors.
73 citations
TL;DR: In this paper, void evolution in Fe ++ -irradiated ferritic-martensitic alloy HT9 was characterized in the temperature range of 400-480°C between doses of 25 and 375 displacements per atom (dpa) with pre-implanted helium levels of 0-100appm.
72 citations
References
More filters
971 citations
TL;DR: In this article, it was shown that the steady-state swelling rate of bcc steels is inherently much lower than that of fcc and that the creep compliance of the two types of alloys also differs only by a factor of about two.
455 citations
TL;DR: In this article, it was shown that all austenitic Fe-Ni-Cr alloys eventually swell during neutron irradiation at a rate of ~1%/dpa over a surprisingly large range of temperature.
158 citations
TL;DR: In this paper, the authors measured the creep and swelling behaviors of HT9 and 9Cr-1Mo at 400°C and 208 dpa, using both diametral and density measurements of helium-pressurized creep tubes.
110 citations
TL;DR: A series of simple (Fe-Cr-C-Mo) ferritic alloy specimens based on the composition of martensitic stainless steels has been examined by transmission electron microscopy following neutron irradiation to a maximum fluence of 4.3 × 1022n/cm2 as mentioned in this paper.
100 citations