Deuterium retention in recrystallized tungsten exposed to high-flux plasma with fluences up to 1 × 10²⁹ m⁻²

Abstract Plasma fluence at the divertor of a future magnetic confinement fusion device can accumulate up to ∼10 28 –10 29 m −2 per year. Yet hydrogen isotope (HI) retention under such high-fluence plasma exposure has been rarely reported. To investigate deuterium (D) retention in tungsten (W) exposed to such high-fluence plasma, a series of high-flux D plasma exposures were preformed using recrystallized W samples at ∼500 K in Magnum-PSI. The highest fluence achieved was ∼1 × 10 29 m −2 . Surface morphology observations indicate an initial increase in the number of blisters at the sample surface with increasing fluence, followed by saturation at ∼1 × 10 29 m −2 . Multiple bursts of blisters with open cracks or edges were observed under the two highest fluences of ∼1 × 10 28 m −2 and ∼1 × 10 29 m −2. 3 He nuclear reaction analysis (NRA) shows a maximum D concentration up to 0.012 at.fr., distributed within the first 4 μ m from the sample surface under the highest fluence. D retention, as measured by NRA and thermal desorption spectroscopy, tends to saturate with increasing fluence. Simulations of D 2 thermal desorption, performed using the TMAP rate equation code, show a maximum D trapping depth of ∼10 μ m, consistent with the defect depth profile revealed by transmission electron microscopy. D retention saturation observed in this work is attributed to the sample surface morphology modifications and the saturation of plasma-induced defects. This investigation provides a valuable reference for understanding the evolution of total HI retention in W under high-fluence plasma exposure in future fusion devices.