Effect of post-D+-irradiation time delay and pre-TDS heating on D retention in single crystal tungsten

Quastel, Adam; Davis, James W.; Haasz, A.A.; Macaulay-Newcombe, R.G.

doi:10.1016/j.jnucmat.2006.07.012

Cited by 38 publications

(43 citation statements)

References 16 publications

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“…Therefore, TDS performed a week after the exposure reveals only strongly trapped deuterium. Similar observations of the decrease in the retained deuterium amount in tungsten over the waiting (storage) time were reported in [6,9,10].…”

Section: Discussionsupporting

confidence: 85%

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Deuterium retention in tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasmas

Zayachuk¹,

Hoen²,

Emmichoven³

et al. 2012

Nucl. Fusion

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A direct comparison of deuterium retention in samples of tungsten and two grades of tungsten-tantalum alloys-W1%Ta and W-5%Ta, exposed to deuterium plasmas (ion flux ∼10 24 m −2 s −1 , ion energy at the biased target ∼50 eV) at the plasma generator Pilot-PSI was performed using thermal desorption spectroscopy (TDS). No systematic difference in terms of total retention in tungsten and tungsten-tantalum was identified. The measured retention value for each grade did not deviate by more than 24% from the value averaged over the three grades exposed to the same conditions. No additional desorption peaks appeared in the TDS spectra of the W-Ta samples as compared with the W target, indicating that no additional kinds of traps are introduced by the alloying of W with Ta. In the course of the experiment the same samples were exposed to the same plasma conditions several times, and it is demonstrated that samples with the history of prior exposures yield an increase in deuterium retention of up to 130% under the investigated conditions compared with the samples that were not exposed before. We consider this as evidence that exposure of the considered materials to ions with energy below the displacement threshold generates additional traps for deuterium. The positions of the release peaks caused by these traps are similar for W and W-Ta, which indicates that the corresponding traps are of the same kind.

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Section: Discussionsupporting

confidence: 85%

“…In order to avoid creation of defects by displacement damage, the energy of the ions was kept well below the displacement damage threshold for D + ions in tungsten (∼940 eV [6]), namely close to 50 eV.…”

Section: Methodsmentioning

confidence: 99%

Deuterium retention in tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasmas

Zayachuk¹,

Hoen²,

Emmichoven³

et al. 2012

Nucl. Fusion

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“…In the literature, few laboratory experiments focused on deuterium dynamic retention in tungsten and all of them have been performed ex situ [2][3][4], i.e. the sample has been brought to air between ion implantation and dynamic retention quantification with thermo-desorption.…”

Section: Introductionmentioning

confidence: 99%

“…However, this powerful method may be not the best one to study the dynamic retention of deuterium because there are some concerns regarding the intrusive aspect of Nuclear Reaction Analysis. Indeed, in this method the probe beam consists of 3 He ions with kinetic energy in the MeV range, being well above most materials displacement threshold energy and defects will be created [7,8]. This could generate a probe-induced evolution of the retention properties of sample materials which would complicate the interpretation of the obtained results.…”

Section: Introductionmentioning

confidence: 99%

Dynamic fuel retention in tokamak wall materials: An in situ laboratory study of deuterium release from polycrystalline tungsten at room temperature

Bisson

Markelj

Mourey.

et al. 2015

Journal of Nuclear Materials

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“…Deuterium release in TDS from tungsten was studied by many researchers as overviews [1,2] demonstrate. Ion implantation is commonly used in these investigations, for example [3][4][5][6][7][8][9][10]. Ions produce radiation defects, which interact with implanted deuterons, so TDS give information about deuterium-defect interaction.…”

Section: Introductionmentioning

confidence: 99%

Investigation of hydrogen-defect interaction in tungsten by the probe fluence method

Rusinov

Gasparyan

Трифонов

et al. 2011

Journal of Nuclear Materials

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Deuterium trapping by defects in W polycrystalline foils during ion bombardment was investigated by thermal desorption spectroscopy using the low fluence probe method. Probe TDS spectra showed, that there are at least 6 peaks in the region 350-900 K: at 370 K, 450 K, 530 K, 580 K, 630 K, 750 K. Experiments with as received samples showed that D is trapped mainly in low energy traps in the region 390-650 K. These defects are attributed to technological defects such as dislocations and vacancies. The peak at 750 K easily disappears when annealing the sample at about 1300 K and can be attributed to vacancy clusters. The peak at 630 K irreversibly increases at high fluence, it also appears when annealing the sample above 1300K. This peak can be attributed to voids. Voids of about 20 nm in diameter in the near surface region were observed by FIB/SEM in cases when 630 K peak was observed.

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Effect of post-D+-irradiation time delay and pre-TDS heating on D retention in single crystal tungsten

Cited by 38 publications

References 16 publications

Deuterium retention in tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasmas

Deuterium retention in tungsten and tungsten–tantalum alloys exposed to high-flux deuterium plasmas

Dynamic fuel retention in tokamak wall materials: An in situ laboratory study of deuterium release from polycrystalline tungsten at room temperature

Investigation of hydrogen-defect interaction in tungsten by the probe fluence method

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