Fuel removal from castellated structures by plasma discharges in hydrogen and oxygen
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference20 articles.
1. Progress in the ITER Physics Basis, Nucl. Fusion, 47, 2007.
2. Tritium inventory in ITER plasma-facing materials and tritium removal procedures
3. Tritium retention in next step devices and the requirements for mitigation and removal techniques
4. Removal of carbon layers by oxygen glow discharges in TEXTOR
5. Deposits removal and hydrogen release on co-deposited films exposed to O-ICR and O-GDC plasmas in HT-7
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1. The upgraded TOMAS device: A toroidal plasma facility for wall conditioning, plasma production, and plasma–surface interaction studies;Review of Scientific Instruments;2021-02-01
2. Fundamental processes of fuel removal by cyclotron frequency range plasmas and integral scenario for fusion application studied with carbon co-deposits;Journal of Nuclear Materials;2015-08
3. Self-consistent application of ion cyclotron wall conditioning for co-deposited layer removal and recovery of tokamak operation on TEXTOR;Nuclear Fusion;2013-11-04
4. Long-term carbon transport and fuel retention in gaps of the main toroidal limiter in TEXTOR;Journal of Nuclear Materials;2013-07
5. Overview of material migration and mixing, fuel retention and cleaning of ITER-like castellated structures in TEXTOR;Journal of Nuclear Materials;2011-08
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