Displacement damage and transmutations in metals under neutron and proton irradiation

Vladimirov, P.; Bouffard, S.

doi:10.1016/j.crhy.2008.02.004

Cited by 41 publications

(39 citation statements)

References 56 publications

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“…Radiation damage by neutrons and by heavy ions is to some extent comparable [7]. For both neutrons and heavy ions, the ratio of low-energy to high-energy primary knock-on atoms is low, and they both create dense collision cascades [8]. However, one should realize that there are also differences between heavy ion and neutron irradiation.…”

Section: W 4+ Irradiationmentioning

confidence: 99%

Saturation of deuterium retention in self-damaged tungsten exposed to high-flux plasmas

Hoen¹,

Tyburska-Püschel²,

Ertl³

et al. 2012

Nucl. Fusion

103

110

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Abstract. Polycrystalline, annealed tungsten targets were bombarded with 12.3 MeV W 4+ ions to various damage levels. Deuterium was implanted by high-flux plasmas in Pilot-PSI ( >10 24 m -2 s -1 ) at a surface temperature below 525 K. Deuterium retention has been studied by Nuclear Reaction Analysis and by Thermal Desorption Spectroscopy. We found that deuterium retention is strongly enhanced by the tungsten bombardment and that saturation occurs at a W 4+ fluence of about 3·10 17 m -2 . The maximum deuterium concentration in the damaged region was measured to be 1.4 at.%. This is in accordance with other experiments that were carried out at much lower fluxes. We therefore conclude that the saturation behaviour and the maximum retention are not affected by the high fluxes used in our experiments.A simple geometric model is presented that assumes that the saturation solely originates in the tungsten irradiation and that explains it in terms of overlapping saturated volumes. The saturated volume per incident MeV ion amounts to 3·10 4 nm 3 . From our results, we are able to obtain an approximate value for the average occupation number of the vacancies.

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Section: W 4+ Irradiationmentioning

confidence: 99%

Saturation of deuterium retention in self-damaged tungsten exposed to high-flux plasmas

Hoen¹,

Tyburska-Püschel²,

Ertl³

et al. 2012

Nucl. Fusion

103

110

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“…The D( 3 He,p) 4 He reaction was utilized, and both the  particles and protons were analyzed. The -spectrum was transformed into a D depth profile at depths up to ~0.5 μm using the program SIMNRA [20].…”

mentioning

confidence: 99%

“…Radiation damage generated by fusion neutrons and by MeV W ions is to some extent comparable [3]. For both neutrons and heavy ions, the energy distribution of primary knock-on atoms peaks at high energies, and they both create dense collision cascades [4]. However, damage created by heavy ions is concentrated in a narrow region below the surface, while neutron-induced damage extends to larger depths.…”

Section: Introductionmentioning

confidence: 99%

The effect of displacement damage on deuterium retention in tungsten exposed to D neutrals and D2 gas

Alimov

Hatano

Sugiyama

et al. 2013

Journal of Nuclear Materials

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Samples of polycrystalline ITER-grade W and recrystallized W were irradiated at room temperature with 20 MeV W ions to displacement damage up to 0.5 dpa. The damaged W samples were then exposed to (i) D neutrals at 403-573 K and (ii) D2 gas at 673-1073 K and pressures of 1.2 and 100 kPa. Trapping of deuterium in the damage zone was examined by the K, on the D 2 gas pressure. Thermal desorption spectra allowed a conclusion that deuterium is mainly accumulated in the form of D atoms bound to inner walls of vacancy clusters.

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“…Self-implantation by tungsten ions has the advantages to be fast, to avoid activation of the sample, and to avoid the introduction of additional impurities which potentially may act as additional trap sites for hydrogen. But it should be kept in mind that tungsten self-implantation mimics neutron effects only to some extend: The maximum primary knock-on atom (PKA) energies and the damage rates are generally higher than by neutrons, while the PKA energy spectrum is softer [3]. The influence of these similarities and differences on radiation damage and hydrogen retention in tungsten is topic of active research.…”

Section: Introductionmentioning

confidence: 99%

Recovery temperatures of defects in tungsten created by self-implantation

Markina

Mayer

Manhard

et al. 2015

Journal of Nuclear Materials

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The recovery of radiation defects in recrystallized tungsten was studied in the temperature range 400 -1150 K. The defects were created by 20 MeV tungsten ions irradiation at room temperature to a maximum damage level of 0.9 dpa. The samples were then annealed to temperatures of 400 to 1150 K for 1 hour in order to anneal the created defects. After annealing the remaining defects were decorated with D by exposing them to a lowtemperature ECR-plasma at 400 K to a fluence of 1x10 25 D/m 2 . Deuterium was detected by nuclear reaction analysis and temperature programmed desorption. Annealing of defects is observed already at slightly elevated temperatures. At 820 K about 50% of the initial defects were annealed, while still about 30% of the initial defects were present after annealing at 1150 K.

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Displacement damage and transmutations in metals under neutron and proton irradiation

Cited by 41 publications

References 56 publications

Saturation of deuterium retention in self-damaged tungsten exposed to high-flux plasmas

Saturation of deuterium retention in self-damaged tungsten exposed to high-flux plasmas

The effect of displacement damage on deuterium retention in tungsten exposed to D neutrals and D2 gas

Recovery temperatures of defects in tungsten created by self-implantation

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