[HTML][HTML] In situ study of thermal shock damage to high-temperature ceramics

DE Cherepanov, LN Vyacheslavov, VA Popov… - Nuclear Materials and …, 2023 - Elsevier
New generations of fusion devices need alternative plasma-facing materials. The currently
approved material composition for the first wall and divertor of the ITER tokamak has a …

Developing solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part A …

PC Stangeby, EA Unterberg, JW Davis… - Plasma Physics and …, 2022 - iopscience.iop.org
It is estimated that pilot plants and reactors may experience rates of net erosion and
deposition of solid plasma facing component (PFC) material of 10 3–10 5 kg yr− 1. Even if …

Comprehensive screening of plasma-facing Materials for nuclear fusion

A Fedrigucci, N Marzari, P Ricci - PRX Energy, 2024 - APS
Plasma-facing materials (PFMs) represent one of the most significant challenges for the
design of future nuclear fusion reactors. Inside the reactor, the divertor will experience the …

Investigation of W-SiC compositionally graded films as a divertor material

Z Lin, C Monton, S Bringuier, G Sinclair… - Journal of Nuclear …, 2024 - Elsevier
W-SiC composite material is a promising plasma-facing material candidate alternative to
pure W due to the low neutron activation, low impurity radiation, and low tritium diffusivity of …

[HTML][HTML] SiC as a core-edge integrated wall solution in DIII-D

S Zamperini, T Abrams, J Nichols, E Unterberg… - Nuclear Materials and …, 2023 - Elsevier
Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low
hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation …

[HTML][HTML] Electrode durability and sheared-flow-stabilized Z-pinch fusion energy

MC Thompson, SC Simpson, CJ Beers, J Dadras… - Physics of …, 2023 - pubs.aip.org
The sheared-flow-stabilized (SFS) Z-pinch concept is on a path to commercialization at Zap
Energy. Recent experiments on the Fusion Z-pinch Experiment (FuZE) and newly …

[HTML][HTML] Computational investigation of incident ion angles and material erosion at rough graphite and silicon carbide divertor surfaces

S Abe, CH Skinner, A Liu, J Garcia, Z Lin… - Physics of …, 2022 - pubs.aip.org
We present a computational investigation of the dependence of material erosion on the
incident ion angle at rough graphite and silicon carbide divertor surfaces. Ion angle …

Computational assessment on impurity sourcing and transport using high-temperature graphite and silicon carbide plasma-facing walls in a tokamak environment

G Sinclair, T Abrams, L Holland - Fusion Science and Technology, 2023 - Taylor & Francis
Operating with hot tokamak plasma-facing components will be essential in fusion reactors to
maximize the thermal efficiency of the blanket. The SOLPS-ITER edge plasma code …

[HTML][HTML] Studies of material deposition on the graphite divertor tile after the 2019 experimental campaign in EAST

W Zheng, R Yan, R Ding, B Gao, B Wang… - Nuclear Materials and …, 2022 - Elsevier
Material erosion and deposition are one of the important topics related to plasma-wall
interaction in tokamaks. Detailed analysis of the deposits on the surface of the graphite tile …

The effectiveness of D2 pellet injection in reducing intra-ELM and inter-ELM tungsten divertor erosion rates in DIII-D during the Metal Rings Campaign

A Cacheris, T Abrams, LR Baylor… - Plasma Physics and …, 2023 - iopscience.iop.org
Edge localized modes (ELMs) in H-mode plasmas erode plasma-facing components (PFCs)
and lead to impurities in the core, reducing confinement. This study analyzes D 2 pellet …