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Journal Articles

Deuterium permeation behavior for damaged tungsten by ion implantation

Oya, Yasuhisa*; Li, X.*; Sato, Misaki*; Yuyama, Kenta*; Oyaizu, Makoto; Hayashi, Takumi; Yamanishi, Toshihiko; Okuno, Kenji*

Journal of Nuclear Science and Technology, 53(3), p.402 - 405, 2016/03

 Times Cited Count:10 Percentile:68.73(Nuclear Science & Technology)

The deuterium (D) permeation behaviors for ion damaged tungsten (W) by 3 keV D$$_{2}$$$$^{+}$$ and 10 keV C$$^{+}$$ were studied. The D permeability was obtained for un-damaged W at various temperatures. For both D$$_{2}$$$$^{+}$$ and C$$^{+}$$ implanted W, the permeability was clearly reduced. But, for the D$$_{2}$$$$^{+}$$ implanted W, the permeability was recovered by heating at 1173 K and it was almost consistent with that for un-damaged W. In the case of C$$^{+}$$ implanted W, the permeability was not recovered even if the sample was heated at 1173 K, indicating that the existence of carbon would prevent the recovery of permeation path in W. In addition, TEM observation showed the voids were grown by heating at 1173 K and not removed, showing the existence of damages would not largely influence on the hydrogen permeation behavior in W in the present study.

Journal Articles

Effect of neutron energy and fluence on deuterium retention behaviour in neutron irradiated tungsten

Fujita, Hiroe*; Yuyama, Kenta*; Li, X.*; Hatano, Yuji*; Toyama, Takeshi*; Ota, Masayuki; Ochiai, Kentaro; Yoshida, Naoaki*; Chikada, Takumi*; Oya, Yasuhisa*

Physica Scripta, 2016(T167), p.014068_1 - 014068_5, 2016/02

 Times Cited Count:30 Percentile:82.55(Physics, Multidisciplinary)

The irradiation defects were introduced by Fe$$^{2+}$$ irradiation, fission neutron irradiation and D-T neutron irradiation. After the irradiation, the deuterium ions (D$$_{2}^{+}$$) implantation was performed and the D retention behavior was evaluated by thermal desorption spectroscopy. The experimental results indicated that dense vacancies and voids within the shallow region near the surface were introduced by Fe$$^{2+}$$ irradiation. The trapping state of D by vacancies and void were clearly controlled by the damage concentration and the voids would become the most stable D trapping site. For fission neutron irradiated W, most of the D was adsorbed on the surface and/or trapped by dislocation loops and no vacancies and voids for D trapping due to its lower damage concentration. D trapping by vacancies were found in the bulk of D-T neutron irradiated W, indicating that the neutron energy distribution could make a large impact on irradiation defect formation and the D retention behavior.

Oral presentation

Effect of irradiation damage profile on hydrogen isotope retention behavior for neutron irradiated tungsten

Fujita, Hiroe*; Yuyama, Kenta*; Uemura, Yuki*; Sakurada, Shodai*; Hu, C.*; Chikada, Takumi*; Oya, Yasuhisa*; Ota, Masayuki; Ochiai, Kentaro

no journal, , 

Tungsten (W) is the candidate for the plasma facing material in D-T fusion reactors. The distribution of defects introduced by neutron irradiation is formed uniformly throughout the bulk, while that by heavy-ion irradiation is concentrated in the shallow region near the surface. Therefore, it is expected that the hydrogen isotope behaviour in neutron irradiated W would be different from that in heavy-ion irradiated W. In this study, the irradiation defects were introduced by Fe$$^{2+}$$ irradiation, fission neutron irradiation and 14 MeV neutron irradiation from D-T fusion reaction. After the irradiation, the deuterium ions (D$$^{2+}$$) implantation was performed and the D retention behaviour was evaluated by thermal desorption spectroscopy (TDS). The experimental results indicate that stable trapping sites would be formed into W by 14 MeV neutron irradiation with lower neutron fluence, on the other hand, only low energy trapping sites will be formed by fission neutron irradiation.

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