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26–28 May 2025
IAEA
Europe/Vienna timezone
7th International Workshop on Models and Data for Plasma-Material Interactions in Fusion Devices (MoD-PMI)

Deuterium Retention Behavior in Tungsten After Plasma Exposure at Varying Temperatures

28 May 2025, 09:30
30m
Press Room (IAEA)

Press Room

IAEA

Vienna International Centre Wagramer Strasse 5 1220 Vienna Austria
invited invited

Speaker

Xiu-Li Zhu (North China Electric Power University)

Description

Temperature plays a critical role in the behavior of deuterium (D) in tungsten (W), a key material for plasma-facing components in fusion reactors. This study investigates the effects of temperature variation on D retention, surface blistering, and defect evolution in W. Two sets of temperature rising (TR) and temperature declining (TD) irradiation experiments were conducted in the temperature ranges of 420 K–590 K and 320 K–720 K.
The deuterium-induced surface blistering behavior was markedly different between the two temperature ranges. In the 420 K–590 K range, the TD exposure resulted in more severe surface blistering, while the TR exposure reduced the formation of intragranular blisters. For the 320 K–720 K irradiation, both TR and TD exposures led to dense blister formation on the tungsten surface, including both intragranular and intergranular blisters, though with different blister densities and average sizes. Statistical analysis of the surface blisters showed that the TD exposure favored the formation of smaller intergranular and intragranular blisters, whereas TR exposure promoted the growth of larger blisters.
In the 320 K–720 K irradiation experiment, both pristine and pre-damaged tungsten were compared to evaluate the influence of temperature variation on the pre-damage effect. The results showed that pre-damage suppressed intragranular blister formation, accelerated intergranular blister growth, and enhanced D retention in both TR and TD exposures, in agreement with previous studies. However, the exacerbating effect on intergranular blisters was more pronounced in the TR exposure, while the suppressive effect on intragranular blisters was reduced under the TD exposure.
Thermal desorption spectra revealed that D retention was significantly higher in the TD exposures compared to the TR exposures. The analysis of deuterium desorption peaks suggests that intrinsic defects in tungsten could evolve and cluster into larger ones in the TR exposure, which acted as higher-energy D traps. The evolution of pre-damaged defects in TR exposure was even more pronounced.
These studies highlight the significant impact of temperature variation during plasma exposure on D behavior and defect evolution in tungsten. Understanding these effects is crucial for optimizing the performance of plasma-facing materials in fusion reactors, where temperature fluctuations during exposure are inevitable.
The above experimental results have been published in the Journal of Nuclear Materials [J Nucl Mater 537 (2020), J Nucl Mater 606 (2025) 155607].

Primary authors

Xiu-Li Zhu (North China Electric Power University) Ting Wang (Beihang University) Zhen-Hua Ke (North China Electric Power University) Yue YUAN (Beihang University) Long Cheng (Beihang University) Guang-Hong Lu (Beihang University)

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