4.7 Article

Annealing of radiation-induced damage in tungsten under and after irradiation with 20 MeV self-ions

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JOURNAL OF NUCLEAR MATERIALS
卷 451, 期 1-3, 页码 379-386

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ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2014.04.011

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  1. Impuls- und Vernetzungsfond der Hemholtz-Gemeinschaft e.V.
  2. Polish Ministry of Science and Higher Education [2855/7.PR EURATOM/2013/2]

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Accumulation and recovery of radiation defects under/after self-ion irradiation in tungsten (W) have been investigated via decoration with deuterium (D) and scanning transmission electron microscopy (STEM). The deuterium was incorporated in damaged material by low-energy D plasma. The D concentration at radiation-induced defects in each sample was subsequently measured by nuclear reaction analysis allowing determination of the D concentration at depths up to 6 mu m. The total D retention was measured by thermal desorption spectroscopy. It was shown that pre-irradiation with self-ions led to rather high D concentration (>= 0.1 at.%) in W even at high temperatures (>= 700 K) due to formation of defects with high de-trapping energy for deuterium. The annealing of defects with low trapping energy for D occurs intensively in the temperature range between 300 and 700 K. The radiation-induced defects with high de-trapping energy for D are thermally stable at least up to 1100 K. The rearrangement and partial healing of dislocations as well as coalescence of small clusters in a big ones accompanied by a reduction of the total density of defects was observed by STEM after annealing of radiation-induced defects in recrystallized tungsten at 1000 K. The D retention monotonically decreases in recrystallized W with increasing of annealing temperature up to 1100 K that is in agreement with the reduction of radiation defect density observed by STEM. However, an increase of the D retention in 'as received' W pre-irradiated with self-ions at annealing temperature of around 1000 K was found. The increase of the D retention at annealing temperature of similar to 1000 K was not observed in the case of recrystallized W pre-irradiated with self-ions. The mechanism of recovery of radiation-induced defects in dependence on the initial intrinsic defects (grain size, impurities, etc.) in W is discussed. (C) 2014 Elsevier B.V. All rights reserved.

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