Sputtering of mixed materials of beryllium and tungsten by hydrogen and helium

Mutzke, A.; Bandelow, G.; Schneider, R.

doi:10.1016/j.jnucmat.2015.05.052

Cited by 14 publications

(9 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Many theoretical studies have focused on this finding [2,10,11,[13][14][15][16][17][18]. By using molecular dynamics simulation, Lasa et al [10] studied the irradiation of Be on W surface at different impacting energies (10-200 eV) and angles (0-75°), and showed that no crystalline alloy structure formed in the W-Be mixed layers after annealing.…”

Section: Introductionmentioning

confidence: 99%

Accumulation of beryllium and its effects on hydrogen retention in tungsten divertor

Chen

et al. 2018

Nucl. Fusion

View full text Add to dashboard Cite

Tungsten (W) and beryllium (Be), as superiorly structural materials, may mutually permeate into each other when used as the plasma-facing materials in a fusion reactor, and interact with hydrogen (H) which commonly exists in the fusion environment. By performing first-principles calculations, we investigate the interactions among W, Be and H in W materials. We find that multiple (up to 10) Be atoms can dissolve in W monovacancy to form nBe-VW complexes, and these complexes can decrease the formation energy of a vacancy nearby, which in turn promotes the growth of nBe-VW complexes. The presence of the nBe-VW complexes reduces the retention of H in vacancy. However, we also find that a small amount of Be dissolved in the small-angle tilt grain boundary (GB) has no obvious influence on H retention, while a large amount of Be will promote the growth of cavities in the GB regions. In addition, the adsorbed Be atoms on W (0 0 1) surface are energetically favorable to aggregate together and form a monolayer structure. The presence of Be atomic layer can weaken the adsorption of H on W surface. This work provides a fundamental insight for understanding the accumulation of Be in W, as well as its effects on H retention. This work did not deal with the case relevant to the Be–W alloying phase, which requires further study.

show abstract

Section: Introductionmentioning

confidence: 99%

Accumulation of beryllium and its effects on hydrogen retention in tungsten divertor

Chen

et al. 2018

Nucl. Fusion

View full text Add to dashboard Cite

show abstract

“…Previous DIII-D experimental and modeling results reveal that there exists a large amount of deposited carbon on the surface of tungsten samples, and the existence of carbon has a noteworthy influence on the tungsten erosion process for both inter-and intra-ELM phases [4,7]. Dynamic simulations for the ITER tungsten divertor also show that the deposited beryllium on the tungsten surface significantly affects the total tungsten erosion rate [18]. However, the complicated mixed-material condition in EAST leads to a challenge for modeling of tungsten divertor erosion.…”

Section: Introductionmentioning

confidence: 94%

An interpretive model for the double peaks of divertor tungsten erosion during type-I ELMs in EAST

Ding

et al. 2021

Nucl. Fusion

View full text Add to dashboard Cite

Double peaks of divertor tungsten erosion during type-I edge-localized modes (ELMs) were observed in the EAST tokamak. To study this unique phenomenon, an analytical model of plasma expansion into vacuum was used to investigate the ELM parallel transport along the magnetic field line to the divertor target. The modeling results reveal that during ELM bursts, the energetic C6+ transport is slower than the main ions due to a lower initial thermal speed. The time of C6+ arriving at the divertor target from the modeling is consistent with the second tungsten erosion peak. Based on the particle flux from the transport model, a newly developed mixed-material model quantitively reproduced the intra-ELM tungsten erosion profiles for both deuterium and helium discharges. A lithium–carbon coating makes the heavier impurity (C6+) comparatively more effective than the main ions on tungsten sputtering, and thus makes the second tungsten erosion peak more remarkable on EAST experiments.

show abstract

“…tungsten fuzz [116]), or heterogeneous materials [117] require specialized codes. SDTrimSP-2D [118] is a MC code with BCA allowing calculating the evolution of two-dimensional targets by implant ation and sputtering [115]. CORTEO [104] allows calculating IBA spectra from arbitrary two-dimensional or threedimensional material distributions [119]; STRUCTNRA [120] calculates IBA spectra from arbitrary two-dimensional distributions.…”

Section: Codes For Two-and Three-dimensional Samplesmentioning

confidence: 99%

Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges

et al. 2019

View full text Add to dashboard Cite

Following the IAEA Technical Meeting on "Advanced Methodologies for the Analysis of Materials in Energy Applications Using Ion Beam Accelerators", this paper reviews the current status of ion beam analysis techniques and some aspects of ion-induced radiation damage in materials for the field of materials relevant to fusion. Available facilities, apparatus development and future research options and challenges are presented and discussed. The analysis of beryllium and radioactivity-containing samples from future experiments in JET or ITER represents not only an analytical but also a technical challenge. A comprehensive list of xxxx-xxxx/xx/xxxxxx 1

show abstract

Sputtering of mixed materials of beryllium and tungsten by hydrogen and helium

Cited by 14 publications

References 8 publications

Accumulation of beryllium and its effects on hydrogen retention in tungsten divertor

Accumulation of beryllium and its effects on hydrogen retention in tungsten divertor

An interpretive model for the double peaks of divertor tungsten erosion during type-I ELMs in EAST

Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges

Contact Info

Product

Resources

About