Hardening effect of multi-energy W²⁺-ion irradiation on tungsten–potassium alloy

【摘要】 Tungsten is one of the most promising plasma-facing materials（PFMs） to be used in the nuclear fusion reactor as divertor material in the future.In this work,W²⁺-ions bombardment is used to simulate the neutron irradiation damage to commercial pure tungsten（W） and rolled tungsten-potassium（W-K）.The 7 MeV of 3×10¹⁵ W²⁺-ions/cm²,3 MeV of 4.5×10¹⁴ W²⁺,and 2 MeV of 3×10¹⁴ W²⁺-ions/cm² are applied at 923 K in sequence to produce a uniform region of 100 nm-400 nm beneath the sample surface with the maximum damage value of 11.5 dpa.Nanoindentation is used to inspect the changes in hardness and elastic modulus after self-ion irradiation.Irradiation hardening occurred in both materials.The irradiation hardening of rolled W-K is affected by two factors:one is the absorption of vacancies and interstitial atoms by potassium bubbles,and the other is the interaction between potassium bubbles and dislocations.Under the condition of 11.5 dpa,the capability of defect absorption can reach a threshold.As a result,dislocations finally dominate the hardening of rolled W-K.Specific features of dislocation loops in W-K are further observed by transmission electron microscopy（TEM） to explain the hardening effect.This work might provide valuable enlightenment for W-K alloy as a promising plasma facing material candidate.更多还原

【Abstract】 Tungsten is one of the most promising plasma-facing materials（PFMs） to be used in the nuclear fusion reactor as divertor material in the future.In this work,W²⁺-ions bombardment is used to simulate the neutron irradiation damage to commercial pure tungsten（W） and rolled tungsten-potassium（W-K）.The 7 MeV of 3×10¹⁵ W²⁺-ions/cm²,3 MeV of 4.5×10¹⁴ W²⁺,and 2 MeV of 3×10¹⁴ W²⁺-ions/cm² are applied at 923 K in sequence to produce a uniform region of 100 nm-400 nm beneath the sample surface with the maximum damage value of 11.5 dpa.Nanoindentation is used to inspect the changes in hardness and elastic modulus after self-ion irradiation.Irradiation hardening occurred in both materials.The irradiation hardening of rolled W-K is affected by two factors:one is the absorption of vacancies and interstitial atoms by potassium bubbles,and the other is the interaction between potassium bubbles and dislocations.Under the condition of 11.5 dpa,the capability of defect absorption can reach a threshold.As a result,dislocations finally dominate the hardening of rolled W-K.Specific features of dislocation loops in W-K are further observed by transmission electron microscopy（TEM） to explain the hardening effect.This work might provide valuable enlightenment for W-K alloy as a promising plasma facing material candidate.更多还原