TY - JOUR
T1 - Surface modification and deuterium retention in hot-rolled potassium doped tungsten alloy exposed to deuterium plasma
AU - Ma, Xiaolei
AU - Wang, Ting
AU - Zhang, Xiaoxin
AU - Yuan, Yue
AU - Cheng, Long
AU - Zhu, Jipeng
AU - Lv, Wei
AU - Lang, Shaoting
AU - Wang, Zihao
AU - Ge, Changchun
AU - Yan, Qingzhi
N1 - Funding Information:
This work was supported by National Natural Science Foundation of China [11905137], ITER-National Magnetic Confinement Fusion Program [2014GB123000], National MCF Energy R&D Program (No. 2019YFE03130002), National Nature Science Foundation of China [51801171] and the Fundamental Research Funds for the Central Universities [2021MS051], Interdisciplinary Innovation Program of North China Electric Power University [XM2112355]. The authors greatly appreciate for the experimental equipment of Beihang University.
Funding Information:
This work was supported by National Natural Science Foundation of China [ 11905137 ], ITER-National Magnetic Confinement Fusion Program [ 2014GB123000 ], National MCF Energy R&D Program (No. 2019YFE03130002 ), National Nature Science Foundation of China [ 51801171 ] and the Fundamental Research Funds for the Central Universities [ 2021MS051 ], Interdisciplinary Innovation Program of North China Electric Power University [ XM2112355 ]. The authors greatly appreciate for the experimental equipment of Beihang University.
Publisher Copyright:
© 2022 Elsevier B.V.
PY - 2022/9
Y1 - 2022/9
N2 - A 25 kg potassium doped tungsten (KW) plate dispersed with ∼71 nm K bubbles was prepared by hot rolling firstly. In order to evaluate the radiation resistance of KW, the surface blistering and deuterium (D) retention were investigated on KW and pure tungsten (PW), which were exposed to low-energy (50 eV) and high-flux (∼1022 D m−2 s−1) D plasmas at 523 K and 573 K to a fluence of 1.08 × 1026 m−2. After irradiation, D desorption information of all the irradiated samples were measured by thermal desorption spectroscopy (TDS). The results indicate that severe blistering occurs on both PW and KW under different irradiation conditions. Compared to PW, KW tends to form more but smaller blisters on the surface. Nevertheless, the blistering area ratio of KW is comparable with that of PW. In addition, the blisters prefer to form on those grains with surface orientation close to (111). In terms of D retention, compared with PW, the total D retention of KW increases by a factor of ∼ 2.5 under both irradiation conditions. The present results indicate that the presence of K bubbles will increase the D retention. The reasons for the difference in surface morphology evolution and total D retention of PW and KW are discussed in detail.
AB - A 25 kg potassium doped tungsten (KW) plate dispersed with ∼71 nm K bubbles was prepared by hot rolling firstly. In order to evaluate the radiation resistance of KW, the surface blistering and deuterium (D) retention were investigated on KW and pure tungsten (PW), which were exposed to low-energy (50 eV) and high-flux (∼1022 D m−2 s−1) D plasmas at 523 K and 573 K to a fluence of 1.08 × 1026 m−2. After irradiation, D desorption information of all the irradiated samples were measured by thermal desorption spectroscopy (TDS). The results indicate that severe blistering occurs on both PW and KW under different irradiation conditions. Compared to PW, KW tends to form more but smaller blisters on the surface. Nevertheless, the blistering area ratio of KW is comparable with that of PW. In addition, the blisters prefer to form on those grains with surface orientation close to (111). In terms of D retention, compared with PW, the total D retention of KW increases by a factor of ∼ 2.5 under both irradiation conditions. The present results indicate that the presence of K bubbles will increase the D retention. The reasons for the difference in surface morphology evolution and total D retention of PW and KW are discussed in detail.
KW - Deuterium plasma exposure
KW - Deuterium retention
KW - Potassium doped tungsten alloy
KW - Surface blistering
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U2 - 10.1016/j.jnucmat.2022.153890
DO - 10.1016/j.jnucmat.2022.153890
M3 - Article
AN - SCOPUS:85132885879
SN - 0022-3115
VL - 568
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 153890
ER -