4.6 Article

Irradiation hardening and deuterium retention behaviour of tungsten under synergistic irradiations of 3.5 MeV Fe13+ ions and deuterium plasma

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NUCLEAR MATERIALS AND ENERGY
卷 34, 期 -, 页码 -

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ELSEVIER
DOI: 10.1016/j.nme.2022.101358

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Tungsten; Heavy -ion irradiation; Displacement damage; Irradiation hardening; Deuterium retention

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This study investigates the irradiation hardening and deuterium retention behavior of tungsten under synergistic irradiations of heavy ions and D plasma. The results show that heavy ion irradiation creates vacancy-type defects and dislocation loops/networks, resulting in irradiation hardening. The interaction between dislocations and damage-induced defects is suggested to be the main source of irradiation hardening. Additionally, the total deuterium retention is increased in the case of pre-irradiation with Fe ions.
This work investigates the irradiation hardening and deuterium (D) retention behaviour of tungsten (W) under synergistic irradiations of heavy ions and D plasma. 3.5 MeV iron (Fe13+) ion irradiation was performed on recrystallized W samples (RW) to produce displacement damage of 1 dpa. Then, low-energy (38 eV) D plasma exposure was conducted at 500 K. It is found that Fe ion irradiation creates substantial vacancy-type defects and dislocation loops/networks in RW. These irradiation-induced defects not only function as nucleation sites for dislocations that increase the activation probability of new dislocations and suppress the pop-in events, but also act as barriers for dislocations that result in irradiation hardening. Nano-indentation results show that the average hardness of RW-D, RW-Fe and RW-Fe-D increases from 5.26 GPa for RW to 5.28, 6.23 and 6.56 GPa, respectively. The strong interaction between dislocations and high density of damage-induced defects is sug-gested to be the chief source for the obvious irradiation hardening observed in the synergistic irradiation case. Besides, compared with RW-D, the total D retention in RW-Fe-D is increased by a factor of 2.65. NRA and TDS results suggest that Fe pre-irradiation not only increases D retention within the damage layer (within the first 1.3 mu m), but also enhances that beyond the damage layer (>1.3 mu m) before surface blisters are formed. This work further improves the fundamental understanding on the microstructure evolution, D retention and nano -mechanical behaviour of W under synergistic irradiation effect of heavy ions and D plasma.

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