Deuterium thermal desorption and re-emission from RAFM steels

Ryabtsev, S.; Gasparyan, Yu. M.; Harutyunyan, Z.; Timofeev, Iu. M.; Огородникова, О. В.; Писарев, А. А.

doi:10.1088/1402-4896/aa878d

Cited by 14 publications

(6 citation statements)

References 11 publications

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“…Exposure to low energy 40 eV deuterium ions resulted in peak at 290 °C [19], similar peak temperature was found for 20 eV ions [20,21]. Exposure to high energy 5 keV D + 3 ions, on the other hand, results in a peak at about 130 °C-170 °C [22]. Our results were obtained after exposure to 400 eV ions, i.e.…”

Section: Discussionsupporting

confidence: 85%

“…Our results were obtained after exposure to 400 eV ions, i.e. the energies are intermediate between those in [19][20][21][22]. They confirm the trend of decreasing temperature of the first peak with increasing energy of deuterium ions.…”

Section: Discussionsupporting

confidence: 81%

“…This possibility should be checked further by modelling H/D release from traps with binding energy about 0.57-0.6 eV that is characteristic for vacancies [23,24]. It is worth noting that in-situ TDS measurements performed 45 minutes after exposure did not reveal more than one peak up to 800 K [22]. Experiments performed with longer delay between exposure and TDS revealed second peak at about 790 K [20] or broad overlapping peaks at 730 and 900 K [19].…”

Section: Discussionmentioning

confidence: 99%

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Comparative study of deuterium retention in irradiated Eurofer and Fe–Cr from a new ion implantation materials facility

et al. 2019

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A new facility to study the interaction of hydrogen isotopes with nuclear fusion relevant first wall materials, its retention and release, has been produced. The new facility allows implanting a range of gases into samples, including tritium. Accurate study of isotope effects, such as the isotopic exchange in damaged microstructure, has previously been difficult due to a background signal of light hydrogen. This new capability will allow virtually background free measurements using tritium and deuterium. The design and build of this facility are described and commissioning results are presented. Within the UKAEA-led Tritium Retention in Controlled and Evolving Microstructure (TRiCEM) project, this facility is used for comparative study of deuterium retention in self-ion irradiated Eurofer steel and Fe-Cr alloy. Self-ion bombardment with energies of 0.5 MeV is used to mimic the defects created by neutrons in fusion power plant and the created traps are then filled with deuterium in the new facility. Implanted samples are analysed using Thermal Desorption Spectrometry (TDS), Secondary Ion Mass Spectrometry (SIMS), and Transmission Electron Microscopy (TEM). Results on total deuterium content as function of time, TDS spectra and SIMS analysis are presented. Comparison of results for Eurofer and Fe-Cr revealed several differences. While some of them may be due to experimental details like different time delays between exposure and analysis, others, such as deuterium retention as function of dose, might be genuine and require further studies.

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Section: Discussionsupporting

confidence: 85%

Section: Discussionsupporting

confidence: 81%

Section: Discussionmentioning

confidence: 99%

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Comparative study of deuterium retention in irradiated Eurofer and Fe–Cr from a new ion implantation materials facility

et al. 2019

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“…The D retention in EU'97 and ODS-16Cr steels exposed at 600 K to low-energy, high flux D and He-seeded D plasmas is low (≤ 3×10 19 D/m 2 ). The reasons for it are (i) enhanced desorption of D from sputter-modified surface, (ii) considerable amount of D has penetrated through the present samples with 0.5-1 mm of the thickness [25,26] and (iii) potentially outgassing between the different measurements [53]. Note that due to the low amount of retained deuterium (≤ 3×10 19 D/m 2 ), errors in the energy-scanning NRA and TDS measurements can reach 50% or even higher.…”

Section: Deuterium and Helium Retentionmentioning

confidence: 93%

Surface modification and deuterium retention in reduced-activation steels exposed to low-energy, high-flux pure and helium-seeded deuterium plasmas

Alimov

Огородникова

Hatano

et al. 2018

Journal of Nuclear Materials

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Surface topography of and deuterium (D) retention in reduced activation ferritic-martensitic Eurofer'97 and ferritic oxide dispersion strengthening ODS-16Cr steels have been studied after exposure at 600 K to low-energy (70 and 200 eV), high-flux (~10 22 D/m 2 s) pure D and D-10%He plasmas with D fluence of 2×10 25 D/m 2. The methods used were scanning electron microscopy, energy-scanning D(3 He,p) 4 He nuclear reaction, and thermal desorption spectroscopy. As a result of the plasma exposures, nano-sized structures are formed on the steel surfaces. After exposure to pure D plasmas, a significant fraction of D is accumulated in the bulk, at depths larger than 8 µm. After exposures to D-He plasmas, D is retained mainly in the near-surface layers. In spite of the fact that the He fluence was lower than the D fluence, the He retention in the steels is one order of magnitude higher than the D retention.

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“…This makes the validity of experiments on post mortem analysis of hydrogen retention in Li-H co-deposits questionable, due to significant film transformations provoked by chemical reactions. Moreover, changes in hydrogen isotopes content is possible even in chemically inert materials after their long time exposure in air [22]. To enhance reliability of gas analyses in co-deposited films in-vacuo experiments must be performed with no contact of deposited films with air after co-deposition.…”

Section: Jinst 15 P01011mentioning

confidence: 99%

A setup for study of co-deposited films

et al. 2020

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A setup for investigation of thermal desorption spectra of gases accumulated in thin films deposited by plasma sputtering of solid targets is described. Deposition and thermal desorption spectroscopy (TDS) are performed in two different vacuum chambers separated by a gate valve with the sample transferred between the chambers in-vacuo. The temperature of the substrate for deposited films can be varied in the range of 300-800 K; and the deposition rate is controlled by a quartz microbalance. Thermal desorption of co-deposited gases is analyzed by a quadrupole mass spectrometer. Sputtering rate and evaporation of the film during TDS are measured by quartz microbalances. Three experiments are described 1) trapping of deuterium by the growing chemically active Li film with subsequent decomposition and evaporation of the film, 2) temperature dependent deuterium trapping in the growing W film resulting in trapping with several binding energies, and 3) chemical interaction of D-Li layer with water vapor leading to isotopic H-D exchange and chemical transformation of the deposited film.

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Deuterium thermal desorption and re-emission from RAFM steels

Cited by 14 publications

References 11 publications

Comparative study of deuterium retention in irradiated Eurofer and Fe–Cr from a new ion implantation materials facility

Comparative study of deuterium retention in irradiated Eurofer and Fe–Cr from a new ion implantation materials facility

Surface modification and deuterium retention in reduced-activation steels exposed to low-energy, high-flux pure and helium-seeded deuterium plasmas

A setup for study of co-deposited films

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