Development of a compact divertor plasma simulator for plasma-wall interaction studies on neutron-irradiated materials

被引:7
作者
Ohno N. [1 ]
Kuwabara T. [1 ]
Takagi M. [1 ]
Nishimura R. [1 ]
Yajima M. [2 ]
Sagara A. [2 ]
Toyama T. [3 ]
Suzuki K. [3 ]
Kurishita H. [3 ]
Shikama T. [3 ]
Hatano Y. [4 ]
Yoshida N. [5 ]
机构
[1] Graduate School of Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya
[2] National Institute for Fusion Science, Oroshi-cho, Toki, Gifu
[3] Institute for Materials Research, Tohoku University, Oarai-machi, Ibaraki
[4] Hydrogen Isotope Research Center, University of Toyama, Toyama
[5] Research Institute for Applied Mechanics, Kyushu University, Kasuga-kouen, Kasuga, Fukuoka
基金
日本学术振兴会;
关键词
Divertor plasma simulator; Hydrogen isotope retention; Neutron-irradiated material; Plasma-wall interaction;
D O I
10.1585/pfr.12.1405040
中图分类号
学科分类号
摘要
We have developed a compact divertor plasma simulator (CDPS) that can produce steady-state deuterium and/or helium plasmas with densities above ~ 1018 m-3 for Plasma-Wall Interaction (PWI) studies of neutronirradiated materials. The maximum particle flux is about 1022 m-2s-1. The CDPS was installed and is being operated in the radiation-controlled area of the International Research Center for Nuclear Materials Science, Institute forMaterials Research, Tohoku University. We are able to control sample temperature within uncertainty of 5 °C during plasma exposure by adjusting the cooling air flow rate to the sample holder. The CDPS has a sample-carrier system, which makes it possible to transfer a plasma-irradiated sample from the sample holder to an infrared heater for analysis using thermal desorption spectroscopy (TDS) without exposing it to the air. This avoids the oxidation of the sample and minimizes the time between the end of plasma exposure and TDS analysis. An ITER-like tungsten (W) sample (A.L.M.T. Corp.), which has been irradiated by neutrons to 0.06 dpa in a fission reactor, was exposed to a deuterium plasma in the CDPS. The experimental results clearly show that the total deuterium retention in the neutron-irradiated W sample increases significantly in comparison with a pristine W, as demonstrated by broadening of the TDS spectrum at high temperatures. © 2017 The Japan Society of Plasma Science and Nuclear Fusion Research.
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