Synthesis of chitosan-acrylic acid/multiwalled carbon nanotubes composite for theranostic 47Sc separation from neutron irradiated titanium target.
Sign Up to like & getrecommendations! Published in 2020 at "International journal of biological macromolecules"
DOI: 10.1016/j.ijbiomac.2020.06.249
Abstract: A simple and efficient separation method of carrier-free 47Sc from neutron irradiated titanium target using a novel chitosan-acrylic acid/multiwalled carbon nanotubes (CS-AA/MWCNTs) composite was established. The synthesis of the CS-AA/MWCNTs composite was achieved using gamma… read more here.
Keywords: irradiated titanium; chitosan acrylic; target; separation ... See more keywords
Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy
Sign Up to like & getrecommendations! Published in 2017 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2016.10.050
Abstract: Abstract FeCrAl alloys are an attractive class of materials for nuclear power applications because of their increased environmental compatibility compared with more traditional nuclear materials. Preliminary studies into the radiation tolerance of FeCrAl alloys under… read more here.
Keywords: fecral alloy; dislocation; dislocation loops; commercial fecral ... See more keywords
Microstructural changes and their effect on hardening in neutron irradiated Fe-Cr alloys
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DOI: 10.1016/j.jnucmat.2019.03.022
Abstract: Abstract A series of Fe-3 to 18 at.% Cr binary ferritic alloys were neutron irradiated side by side, in the Advanced Test Reactor (ATR) at a temperature of ∼320 °C to a dose of ∼1.8 dpa. Three… read more here.
Keywords: microstructural changes; neutron irradiated; irradiated alloys; changes effect ... See more keywords
A transmission electron microscopy study of EBR-II neutron-irradiated austenitic stainless steel 304 and nickel-base alloy X-750
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DOI: 10.1016/j.jnucmat.2019.151851
Abstract: Abstract The microstructure of EBR-II neutron-irradiated austenitic stainless steel 304 and nickel-base alloy X-750 was investigated. Both alloys were irradiated at low dose rates (∼2 × 10−8 dpa/s) to a neutron fluence of 6.9 × 1022 n/cm2 (E > 0.1 MeV) at… read more here.
Keywords: stainless steel; neutron irradiated; ebr neutron; microscopy ... See more keywords
Nano-hardening features in high-dose neutron irradiated Eurofer97 revealed by atom-probe tomography
Sign Up to like & getrecommendations! Published in 2020 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2020.152228
Abstract: Abstract High dose (15 and 32 dpa), 300–330 °C neutron irradiated Eurofer97 samples (WTZ, ARBOR-I and SPICE campaigns) have been analysed using atom probe tomography. Segregation of solutes (Si, P, Mn and sometimes Cr and Ni)… read more here.
Keywords: atom probe; high dose; neutron irradiated; probe tomography ... See more keywords
Direct observation of dislocation loops shrinkage upon annealing neutron-irradiated Fe–9Cr alloy
Sign Up to like & getrecommendations! Published in 2020 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2020.152401
Abstract: Abstract Post-irradiation annealing is an effective way to recover mechanical properties by removing neutron damage. Using in-situ transmission electron microscopy, a neutron irradiated Fe–9Cr alloy was annealed under specific time-temperature scheme. In general, dislocation loops… read more here.
Keywords: irradiated 9cr; dislocation loops; neutron irradiated; shrinkage ... See more keywords
α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel
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DOI: 10.1016/j.jnucmat.2020.152536
Abstract: Abstract To develop metallic fuel with ultra-high burnup of 30%-40%, an annular U-10Zr fuel with 55% smear density was fabricated through a casting route and irradiated at the Advanced Test Reactor at Idaho National Laboratory.… read more here.
Keywords: neutron irradiated; metallic fuel; fission gas; fuel ... See more keywords
Recovery behavior of neutron-irradiated aluminum nitride with and without containing interstitial dislocation loops
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DOI: 10.1016/j.jnucmat.2020.152584
Abstract: Abstract Recovery behavior of the same AlN but neutron-irradiated with different conditions was studied by using XRD and dilatometry. Length recovery rates at each isothermal annealing step were analyzed by first to second-order kinetics. The… read more here.
Keywords: recovery; temperature; recovery behavior; energy ... See more keywords
Early-stage microstructural evolution and phase stability in neutron-irradiated ferritic-martensitic steel T91
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DOI: 10.1016/j.jnucmat.2021.153207
Abstract: Abstract A Fe-9Cr ferritic martensitic (F/M) steel T91 was neutron-irradiated in the Advanced Test Reactor up to 3.96 dpa in two temperature ranges, 466 °C to 534 °C and 571 °C to 632 °C. The microstructure evolution including dislocation loops,… read more here.
Keywords: ferritic martensitic; neutron irradiated; martensitic steel; steel t91 ... See more keywords
Growth and ripening of oxygen precipitation in neutron-irradiated Czochralski silicon
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DOI: 10.1016/j.mssp.2017.11.010
Abstract: Abstract The effects of the vacancy-related defects introduced by neutron irradiation on oxygen precipitation in Czochralski silicon have been elaborately investigated. It is found that the vacancy-related defects significantly enhance the nucleation of oxygen precipitates… read more here.
Keywords: oxygen; oxygen precipitates; czochralski silicon; oxygen precipitation ... See more keywords
The CO V defect in neutron irradiated silicon: An infrared spectroscopy study
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DOI: 10.1016/j.mssp.2017.11.044
Abstract: We report infrared (IR) spectroscopy studies on defects in carbon containing neutron irradiated Czochralski grown silicon (Cz-Si). Prior to irradiation the material was subjected to high temperature treatments (HT) at 1000 °C. Two weak bands at… read more here.
Keywords: infrared spectroscopy; neutron irradiated; spectroscopy; irradiated silicon ... See more keywords