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...
Main Authors: | , , , , , , , , |
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Format: | Article |
Language: | English |
Published: |
Elsevier
2022-09-01
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Series: | Nuclear Materials and Energy |
Subjects: | |
Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179122001016 |