Deuterium desorption from tungsten using laser heating

Yu, J. H.; Simmonds, M.; Baldwin, M.J.; Doerner, R.

doi:10.1016/j.nme.2016.10.017

Cited by 18 publications

(15 citation statements)

References 24 publications

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“…The thermally desorbed particle flux was calculated by converting the QMS measured partial pressure via a calibrated D 2 leak. The total D flux was calculated as described in further detail by Yu [25], as the sum of the HD and twice the D 2 flux. Note that the HD flux was calibrated to the D 2 leak, without any further correction for ionization efficiency.…”

Section: Final Tdsmentioning

confidence: 99%

Isolating the detrapping of deuterium in heavy ion damaged tungsten via partial thermal desorption

Simmonds

Schwarz-Selinger

et al. 2019

Journal of Nuclear Materials

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Partial Thermal Desorption Spectrometry (pTDS) progressively depopulated trapped deuterium (D) from heavy-ion damaged tungsten (W) to determine spatial location and detrapping energies. W samples were prepared identically: 5 MeV Cu 2+ damaging ions (0.12 peak dpa dose) before D 2 plasma loading (10 24 D/m 2 fluence) held at 373 K. Each sample reached one of six pTDS peak-and-hold temperatures. Nuclear Reaction Analysis (NRA) measured the D spatial profile remaining after pTDS, before final TDS. NRA and TDS measured total D retention were in good agreement. NRA displayed three zones of D-populated defects: (I) near-surface (below 0.1 µm), (II) heavy-ion damage (peaked ∼1 µm), and (III) uniform intrinsic (bulk). D concentration in zone I reduced by ∼ 97% in samples with pTDS at 597 K and higher, indicating near-surface traps have low detrapping energy. The Stopping and Range of Ions in Matter (SRIM) predicts a displacement profile

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Section: Final Tdsmentioning

confidence: 99%

Isolating the detrapping of deuterium in heavy ion damaged tungsten via partial thermal desorption

Simmonds

Schwarz-Selinger

et al. 2019

Journal of Nuclear Materials

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“…-в модельных описаниях обычно используют два-три типа ловушек и пытаются связать их с некими дефектами кристаллической структуры (единичные вакансии, несколько атомов водорода в одной вакансии, вакансионные кластеры, газонаполненные пузырьки, дислокационные петли, хем осорбция на стенках полостей, атомы примесей) или просто делят ловушки на «присущие материалу» и «созданные в результате повреждений». Характерная энергия выхода водорода из ловушек в чистом вольфраме не превышает 2,1 эВ [23,[37][38][39]. Примесь может создавать более глубокие ловушки водорода в вольфраме [40]; -поскольку захват водорода в вольфраме определяется дефектами кристаллической структуры материала, накопление водорода в вольфраме зависит от технологии его производства, вплоть до мелких нюансов, способа подготовки и индивидуальной истории конкретного образца.…”

Section: особенности накопления водорода в вольфрамеunclassified

Hydrogen Retention in Doped Tungsten Materials Developed for Fusion

Голубева¹,

Черкез²

2018

PAST-TF

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Данный обзор посвящён влиянию легирования различными элементами на накопление в вольфраме. Вольфрам-один из наиболее перспективных обращённых к плазме материалов (ОПМ), обладающий тем не менее рядом недостатков. Для повышения пригодности вольфрама в качестве ОПМ предлагают легировать вольфрам различными добавками. К настоящему времени в рамках термоядерных разработок создано достаточно большое количество сплавов вольфрама. Легирование может изменить накопление водорода в вольфраме, и это должно быть тщательно учтено при выборе материалов для использования в термоядерных установках.

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“…Figure 5 compares the current values of / Γ Γ in ion as a function of Γ ion , with those of the literature and is plotted without regard to the incident ion energy. In assembling this plot the val(2d) analysis [26] of the data of Hino et al [34] is used as well as the results of TMAP simulations (not shown) of TDS data from [35] and figure 1 in [10]. There is an obvious and definitive trend in the data.…”

Section: Experiments Amentioning

confidence: 99%

“…In similar work [15] approximately 30% of the He inventory was released up to 1273 K, and evidence of such release can be seen in figure 2 Plot of ( / ) Γ Γ log in ion required in Tmap simulations against ( ) Γ log ion for control samples A-1 and B-1 (×), compared to data of the literature. ( ) [26,34], (◊) [35], ( ) [10] and [32]. Error bars on PISCES data reflect the degree to which simulation gives a reasonable fit to TDS data.…”

Section: Experiments Bmentioning

confidence: 99%

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Hydrogen isotope transport across tungsten surfaces exposed to a fusion relevant He ion fluence

Baldwin

Doerner

2017

Nucl. Fusion

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Tungsten targets are exposed to controlled sequences of D 2 and He, and He and D 2 plasma in the Pisces-A linear plasma device, with a view to studying the outward and inward transport of D across a He implanted surface, using thermal desorption mass spectrometry. Differences in transport are interpreted from changes in peak desorption temperature and amplitude for D 2 release, compared against that of control targets exposed to just D 2 plasma. Desorption data are modeled with Tmap-7 to infer the nature by which He leads to the 'reduced inventory' effect for H isotope uptake. A dual segment (surface-30 nm, bulk) W Tmap-7 model is developed, that simulates both plasma exposure and thermal desorption. Good agreement between desorption data and model is found for D 2 release from control targets provided that the implanted flux is reduced, similar to that reported by others. For He affected release, the H isotope transport properties of the surface segment are adjusted away from control target bulk values during the computation. Modeling that examines outward D transport through the He implanted layer suggests that a permeation barrier is active, but bubble induced porosity is insufficient to fully explain the barrier strength. Moderately increased diffusional migration energy in the model over the He affected region, however, gives a barrier strength consistent with experiment. The same model, applied to inward transport, predicts the reduced inventory effect, but a further reduction in the implanted D flux is necessary for precise agreement.

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Deuterium desorption from tungsten using laser heating

Cited by 18 publications

References 24 publications

Isolating the detrapping of deuterium in heavy ion damaged tungsten via partial thermal desorption

Isolating the detrapping of deuterium in heavy ion damaged tungsten via partial thermal desorption

Hydrogen Retention in Doped Tungsten Materials Developed for Fusion

Hydrogen isotope transport across tungsten surfaces exposed to a fusion relevant He ion fluence

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