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Development of an in operando uniaxial fatigue testing regime for the linear plasma device Magnum-PSI

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Abstract
Tokamak divertors may be exposed to cyclic thermomechanical loads during service, giving rise to the fatigue cracking of plasma-facing monoblocks. Fatigue is a surface-sensitive dislocation-mediated degradation phenomenon, and monoblock fatigue life may be affected by plasma-material interactions such as D/T/He implantation, blistering, fuzz, and ELMs that modify the morphology, microstructure and mechanical response of the plasma-facing surface. To investigate the synergistic effects of plasma-material interactions on fatigue cracking, a novel experimental method has been developed for the Magnum-PSI linear plasma device that combines cyclic thermomechanical loading with simultaneous plasma exposure. A DEMO strikepoint sweeping scenario (45 MW m−2 at 1 Hz over 100 mm span) is translated into experimental parameters via time-dependent thermal–mechanical finite element modelling of a monoblock, which calculated the uniaxial strain imposed at the centre of the plasma-facing surface to be 0.648%. The cyclic thermal loading of ITER-grade W targets is achieved in Magnum-PSI via sinusoidal modulation of the plasma source, with real-time monitoring via synchronous Thomson scattering, optical emission spectroscopy, pyrometry, and infrared thermography. Initial results are presented which demonstrate a proof-of-concept in operando fatigue testing method, qualitatively explore surface roughness/treatment effects, and indicate that strikepoint sweeping may significantly contribute to plasma-facing surface cracking.
Year of Publication
2026
Journal
Nuclear Materials and Energy
Volume
47
Number of Pages
102119
Date Published
06/2026
DOI
PId
9f5e944cc1799757569e528199430226
Alternate Journal
Nucl. Mater. Energy
Label
OA
Journal Article
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Citation
Hargreaves, J., Vernimmen, J. W. M., Scholten, J., Brons, S., & Morgan, T. W. (2026). Development of an in operando uniaxial fatigue testing regime for the linear plasma device Magnum-PSI. Nuclear Materials and Energy, 47, 102119. https://doi.org/10.1016/j.nme.2026.102119 (Original work published 2026)