@article{a2e52ae8dbe14703a92bdcc824600f39,
title = "Neutron irradiation tolerance of potassium-doped and rhenium-alloyed tungsten",
abstract = "Tungsten (W) based materials for fusion reactor applications have been developed in Japan for the last decade to improve thermo-mechanical properties and tolerance with respect to neutron-irradiation effects. Potassium (K) doping for dispersion strengthening and alloying by rhenium (Re) for solid solute softening and strengthening were applied to W fabricated by powder metallurgy. Thereby modified W materials, e.g. K-doped W and K-doped W-3%Re, demonstrated a higher recrystallization temperature threshold, an increase in strength and ductility, and a reduction in ductile-to-brittle transition temperature (DBTT) compared to pure W in the non-irradiated state. Embrittlement caused by displacement damage and its amplification due to solid transmutation products is expected to be an intrinsic issue of W based materials under neutron irradiation environment inherent to future fusion reactors. In this paper, the effect of K-doping and alloying by Re on the neutron-irradiation-induced embrittlement of W was investigated at neutron fluence causing a considerable amount of solid transmutation products.",
keywords = "Alloying by rhenium, Embrittlement, Neutron irradiation, Potassium doping, Tungsten",
author = "Shuhei Nogami and Dmitry Terentyev and Aleksandr Zinovev and Chao Yin and Michael Rieth and Gerald Pintsuk and Akira Hasegawa",
note = "Funding Information: This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 and 2019–2020 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization or of the European Commission. This work was also supported by JSPS KAKENHI Grant Number 15KK0224, 26289351, 24246151, 17H01364, and 18H01196 in Japan. In addition, this work was performed with the support and under the auspices of the National Institute for Fusion Science (NIFS) Collaboration Research program (NIFS11K0BF019) in Japan. Authors are also grateful to Mr. T. Takida, Mr. S. Nakabayashi, and Mr. N. Matsuda of A.L.M.T. Corp. for their support to our material development. Funding Information: This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014?2018 and 2019?2020 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization or of the European Commission. This work was also supported by JSPS KAKENHI Grant Number 15KK0224, 26289351, 24246151, 17H01364, and 18H01196 in Japan. In addition, this work was performed with the support and under the auspices of the National Institute for Fusion Science (NIFS) Collaboration Research program (NIFS11K0BF019) in Japan. Authors are also grateful to Mr. T. Takida, Mr. S. Nakabayashi, and Mr. N. Matsuda of A.L.M.T. Corp. for their support to our material development. Publisher Copyright: {\textcopyright} 2021 Elsevier Ltd",
year = "2021",
month = sep,
doi = "10.1016/j.jnucmat.2021.153009",
language = "English",
volume = "553",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",
}