Tungsten erosion under simulation of iter divertor operation

Guseva, M. I.; Gureev, V.M.; Danelyan, L.S.; Kolbasov, B.N.; Korshunov, S. N.; Martynenko, Yu. V.; Petrov, V.B.; Stolyarova, V. G.; Khripunov, B.I.; Vasiliev, V. I.; Strunnikov, V. M.

doi:10.1080/1051999031000120153

Cited by 7 publications

(5 citation statements)

References 5 publications

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“…Therefore, simulation experiments have shown that the neighborhood of carbon leads to the intensification of the erosion process of tungsten. One need to note that this result is in the contradiction with the prediction of the authors of work [12], stating that the erosion of mixed layers of tungsten and carbon is lower than one for pure tungsten.…”

Section: Influence Of Mutual Neighborhood Of Tungsten and Graphite Oncontrasting

confidence: 81%

Simulation of iter transient heat loads to the divertor surfaces with using the powerful quasi-steady-state plasma accelerator

et al. 2006

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The results of experiments on powerful plasma stream -surface interaction in conditions of heat loads typical for current disruptions in reactor-tokamak ITER are presented here. The long pulse powerful plasma streams are generated with quasi-steady-state plasma accelerator QSPA Kh-50. The morphology of surfaces of tungsten and graphite, as well as surface of combined tungsten-graphite targets exposed to powerful plasma streams is analyzed. Some erosion properties of these materials are presented and compared with results of numerical simulations.PACS : 52.40.Hf

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Section: Influence Of Mutual Neighborhood Of Tungsten and Graphite Oncontrasting

confidence: 81%

Simulation of iter transient heat loads to the divertor surfaces with using the powerful quasi-steady-state plasma accelerator

et al. 2006

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“…The He incident energy of 90 eV is insufficient to induce the W sputtering because the physical sputtering threshold is about 105-110 eV [30,31]. The W subthreshold sputtering only came from weakly bonded, absorbed on the surface, loose adatoms [36]. Its concentration on the surface is usually very low [36], resulting in a low subthreshold sputtering yield.…”

Section: The Particle Behavior Under He Irradiationmentioning

confidence: 99%

“…The W subthreshold sputtering only came from weakly bonded, absorbed on the surface, loose adatoms [36]. Its concentration on the surface is usually very low [36], resulting in a low subthreshold sputtering yield. While 90 eV is much higher than the sputtering threshold energy for Zr (both in ZrC and ZrO 2 ), resulting in a relatively high sputtering yield.…”

Section: The Particle Behavior Under He Irradiationmentioning

confidence: 99%

“…Considering the experimental temperature of 920 • C and the He ion energy of 90 eV in this paper, some W atoms could be sputtered from the extended fuzz below the physical sputtering threshold and deposited on the particle. The concentration of adatoms on the surface is usually very low [36], resulting in a low subthreshold sputtering yield. The general sputtering/deposition process [37] is that atoms gather into clusters, and then gradually extend into layers.…”

Section: The Growth Of the Fuzz Layermentioning

confidence: 99%

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Surface modification of ZrC dispersion-strengthened W under low energy He plasma irradiation

Li,

Liu,

Chen

et al. 2024

Nucl. Fusion

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ZrC dispersion-strengthened W exhibits high strength/ductility, low ductile-to-brittle transition temperature, and excellent thermal shock resistance, making it a promising candidate plasma-facing material for future fusion devices. In this study, surface modification of 0.5 wt.% ZrC dispersion-strengthened W (WZrC) under low energy and high fluence He plasma irradiation at high temperature was presented. Under the energy of 90 eV and fluence ranging from 6 × 1024 He∙m-2 to 2 × 1026 He∙m-2 He irradiation at 920 ℃, typical fuzz nanostructure appeared on the W matrix of WZrC. The fuzz showed comparable thickness and structure features to pure W, which indicates limited effects of the particle’s addition on resistance to high fluence He irradiation at high temperatures. Besides, the erosion behavior of particles under He plasma irradiation has been investigated, which is thought to be dominated by a sputtering process. Under the He influence of 6 × 1024 He∙m-2, only nanopores were observed in the surface region. With fluence increasing to 5 × 1025 He∙m-2, the surface became relatively uneven with larger holes and stalagmitic structures. And W accumulated on the top of stalagmitic structures due to the subthreshold sputtering under He irradiation. When fluence further increased to 2 × 1026 He∙m-2, the particles were eroded completely and covered by the extended fuzz, forming cavities. In addition, distinctive layered nanotendrils were observed above the cavities, which were characterized to be consist of inner W-riched skeletons and outer Zr-riched layers. It indicates that the layered nanotendrils should be the result of fuzz extension combined with particles sputtering and redeposition.

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“…Нами, например, наблюдались ранее модификация поверхности вольфрама в дейтериевой плазме при очень низких энергиях ионов и высоких флюенсах облучения и явление подпорогового распыления [2], причём на поверхности наблюдалось появление наноразмерной структуры [3]. При воздействии дейтериевой плазмы на графит РГ-Т (РФ) мы также наблюдали изменение поверхности.…”

Section: Introductionunclassified

Tungsten and Carbon Surface Change Under High Dose Plasma Exposure

Martynenko¹,

Khripunov²,

Petrov

2009

PAST-TF

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На плазменной установке ЛЕНТА с прямым магнитным полем исследована динамика состава поверхности материалов. Экспозиции в стационарной плазме были подвергнуты вольфрам WL 10, содержащий 1% La 2 O 3, и графит РГ-Т с добавкой титана. Дозы ионов, полученные на поверхности, составили ≥ 10 21 ионсм-2. Эксперименты проведены при различных энергиях ионов и температурах поверхности, использованы также различные рабочие газы. Вольфрам WL 10 облучён в дейтериевой плазме при энергии ионов ~20 и 200 эВ при температуре 340 К. Экспозиция графита РГ-Т проводилась при температуре 1400 К (моделирование временных интервалов между событиями ELM). Повышенная температура (около 1050 К) была также реализована в экспериментах с вольфрамом, облучавшимся в азотной плазме. Наблюдалось изменение микроструктуры поверхности, обнаружено изменение состава поверхности материалов, отражающее влияние больших потоков плазмы на перераспределение элементов в поверхностных слоях. Ключевые слова: вольфрам, графит, модификация поверхности, экспозиция в плазме. TUNGSTEN AND CARBON SURFACE CHANGE UNDER HIGH DOSE PLASMA EXPOSURE. Yu.V. MARTYNENKO, B.I. KHRIPUNOV, V.B. PETROV. Study of surface composition dynamics has been made on the LENTA linear plasma simulator. Experiments have been made on tungsten and carbon materials subjected to steady-state plasma exposure. The achieved ion doses on the surface were at. ≥ 10 21 ioncm-2. WL 10 tungsten containing 1% of La 2 O 3 and titanium-doped graphite RG-T were studied. Energy of ions, surface temperature and working gas were varied in these experiments. Irradiations of tungsten WL 10 were executed in deuterium plasma at ion energies ~20 and 200 eV at temperatures below 340 K. Graphite RG-T was exposed at 1400 K (simulated inter-ELMs condition). Elevated surface temperature (about 1050 K) was also characteristic of experiments on tungsten under nitrogen plasma impact. Surface microstructure modification has been observed and surface composition changes were found on the materials showing influence of high dose plasma on element redistribution in the near surface layers.

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Tungsten erosion under simulation of iter divertor operation

Cited by 7 publications

References 5 publications

Simulation of iter transient heat loads to the divertor surfaces with using the powerful quasi-steady-state plasma accelerator

Simulation of iter transient heat loads to the divertor surfaces with using the powerful quasi-steady-state plasma accelerator

Surface modification of ZrC dispersion-strengthened W under low energy He plasma irradiation

Tungsten and Carbon Surface Change Under High Dose Plasma Exposure

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