Baseline high heat flux and plasma facing materials for fusion

Ueda, Y.; Schmid, K.; Balden, M.; Coenen, J. W.; Loewenhoff, Thorsten; Ito, Atsushi; Hasegawa, Akira; Hardie, Christopher D.; Porton, M.; Gilbert, Mark R.

doi:10.1088/1741-4326/aa6b60

Cited by 158 publications

(104 citation statements)

References 308 publications

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“…The resulting localized hot spots can further be initial sources of transient spot melting and potential splashing and contamination problem that are currently being actively studied by the fusion community. 47 The contribution of the Fig. 5) (a) and temporal distribution (b) of the particle and radiation power fluxes and the resulting surface temperature.…”

Section: -11mentioning

confidence: 99%

Comprehensive 3-D simulation and performance of ITER plasma facing and nearby components during transient events—Serious design issues

Sizyuk

Hassanein

2018

Physics of Plasmas

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A key obstacle to a successful magnetic fusion energy production in Tokamak reactors is performance during abnormal events. Abnormal events include plasma disruptions, edge-localized modes (ELMs), vertical displacement events, and runaway electrons. While tremendous efforts are being made to find ways to mitigate such events, a credible reactor design must be able to tolerate a few of these transient events. We have recently enhanced our comprehensive HEIGHTS (High Energy Interaction with General Heterogeneous Target Systems) simulation package to enable detailed 3-D investigation of the overall aspects of plasma-material interaction processes during all the transient events. Advanced models and numerical tools were developed to efficiently couple major key processes during the transient events, and in particular disruptions and giant ELMs. These include dynamic interaction, deposition, and scattering of the escaping core plasma particles with the evolving and propagating secondary divertor vapor/plasma in the strong magnetic field. These details are critical for assessing the damage to all interior components, including the hidden structure and the first wall which were not directly exposed to these transient events and never thought to be affected as a result. Despite developing numerous efficient numerical techniques and solution methods, such calculations take several months on current supercomputers to complete. Our present results show, for the first time, that unmitigated transient events could cause significant melting and vaporization damage to most interior and hidden components, including the first wall that were not directly exposed to these events. The current ITER divertor design may not work properly and need to be significantly modified or redesigned to prevent this damage. Published by AIP Publishing. https://doi.

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Section: -11mentioning

confidence: 99%

Comprehensive 3-D simulation and performance of ITER plasma facing and nearby components during transient events—Serious design issues

Sizyuk

Hassanein

2018

Physics of Plasmas

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“…Low‐energy He ions, whose incident energy is lower than 10 eV, are especially likely to contribute to the further growth of fuzz when combined with cyclic precipitation of high‐energy ions . As the fuzz formation would lead to significant thermal and electrical property changes, these morphology changes should be regarded as an important factor when evaluating the erosion properties of divertor plates …”

Section: Introductionmentioning

confidence: 99%

“…So far, the arcing in fusion‐relevant devices has been reported in: JT‐60U, LHD, ASDEX‐U, and DIII‐D . Arc ignition is harmful to fusion devices because it can be a cause of erosion of PFC and an impurity source to a core plasma . As the first laboratory experiment was conducted in 2009, much subsequent research has characterized several properties of the arcing, including ignition and duration conditions .…”

Section: Introductionmentioning

confidence: 99%

Ignition and erosion of materials by arcing in fusion‐relevant conditions

Hwangbo

Kajita

Barengolts

et al. 2018

Contributions to Plasma Physics

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This study investigated the characteristics of arcing initiated on nanostructured fuzzy tungsten (W) surfaces in helium (He) plasmas. Under the same He plasma conditions, the relationship between arc voltage and current was characterized as linear due to plasma resistance across the He plasma from the target surface to the plasma source. Properties of the erosion caused by arcing were investigated by focusing on two parameters: arc current and fuzzy layer thickness. The erosion per charge was significantly dependent on the thickness of the fuzzy layer but did not depend on the arc current. Sample surface analysis revealed that drastic changes in arc spot grouping features were accompanied by the fuzzy layer thickness variation. The ecton model indicated that the erosion as ions does not play a main role, but mechanical destruction by momentum transfer from the explosive electron emission centre to neighbouring nanowires seems to enhance the erosion greatly.

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“…Furthermore, harsh irradiation conditions including the high-flux particles, heat loading, and neutron damage will degrade the mechanical properties of W and increase its DBTT [6]. Advanced W-based materials with high performances which can keep the structure sound even under the harsh irradiation condition are required [7]. The reinforcement approaches usually involve alloying, nanostructuring, and the material design.…”

Section: Introductionmentioning

confidence: 99%

Recent studies of tungsten-based plasma-facing materials in the linear plasma device STEP

et al. 2019

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This contribution summarized the recent studies of tungsten-based plasma-facing materials in the linear plasma device like the simulator for tokamak edge plasma (STEP), focusing on the examination of newly developed tungsten (W)-based materials and plasma-induced defects in pure W. Pure W, W-V, W-Y 2 O 3 and W-ZrC samples were exposed to a high-flux plasma of ~ 10 21 -10 22 m −2 s −1 with a fluence up to 10 26 m −2 at a surface temperature below 500 K. The investigation of fundamental evolution of plasma-induced defects in pure W indicated a critical role of hydrogen-dislocation interactions. Suppressed surface blistering was observed in all W-based materials, but deuterium desorption behavior and retention were distinct with respect to different materials. The studies showed that the linear plasma device like the STEP was indispensable in the understanding of plasma-material interactions and the qualification of new materials for future fusion reactors.

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Baseline high heat flux and plasma facing materials for fusion

Cited by 158 publications

References 308 publications

Comprehensive 3-D simulation and performance of ITER plasma facing and nearby components during transient events—Serious design issues

Comprehensive 3-D simulation and performance of ITER plasma facing and nearby components during transient events—Serious design issues

Ignition and erosion of materials by arcing in fusion‐relevant conditions

Recent studies of tungsten-based plasma-facing materials in the linear plasma device STEP

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