In-situ TEM Study of Dislocation Loop Evolution in Tungsten under Dual-ion Beam Irradiation

In-situ TEM Study of Dislocation Loop Evolution in Tungsten under Dual-ion Beam Irradiation

Fusion reactors are regarded as the ultimate source of energy for addressing future power problems. However, prior to the building of fusion power plants, a number of scientific obstacles including significant degradation of plasma-facing material (PFM). Due to its excellent irradiation resistance a...

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Bibliographic Details
Main Author: MA Pengfei1, LIU Yan2, CAO Liuxuan2, ZHANG Yapei1, LI Xiurui1, TIAN Wenxi1, QIU Suizheng1, SU Guanghui1
Format: Article
Language:English
Published: Editorial Board of Atomic Energy Science and Technology 2025-04-01
Series:Yuanzineng kexue jishu
Subjects:
plasma-facing material
tungsten
dual-ion beam irradiation
in-situ tem
dislocation loop
Online Access:https://yznkxjs.xml-journal.net/article/doi/10.7538/yzk.2024.youxian.0600
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https://yznkxjs.xml-journal.net/article/doi/10.7538/yzk.2024.youxian.0600

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