Dependence of deuterium retention and surface blistering on deuterium plasma exposure temperature and fluence in lanthanum oxide doped tungsten

Oxide dispersion strengthened tungsten (ODS-W) is a potential candidate for plasma-facing materials (PFMs) in future fusion reactors. In this work, deuterium (D) retention and surface blistering in W-1 wt% La2O3 (W-La2O3) have been investigated after exposure to low-energy (40 eV) D plasma with vari...

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Bibliographic Details
Main Authors: Yuhan Sun, Shiwei Wang, Chen Li, Wangguo Guo, Yue Yuan, Hong Zhang, Peng Wang, Long Cheng, Guang-Hong Lu
Format: Article
Language:English
Published: Elsevier 2022-09-01
Series:Nuclear Materials and Energy
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179122001016