Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data
Author:
Funder
Euratom
Fundação para a Ciência e a Tecnologia
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics
Reference16 articles.
1. Plasma-surface interaction in the Be/W environment: Conclusions drawn from the JET-ILW for ITER
2. Long-term fuel retention in JET ITER-like wall
3. Global erosion and deposition patterns in JET with the ITER-like wall
4. Material migration patterns and overview of first surface analysis of the JET ITER-like wall
5. Overview of erosion–deposition diagnostic tools for the ITER-Like Wall in the JET tokamak
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2. Fuel desorption from JET-ILW materials: assessment of analytical approach and identification of sources of uncertainty and discrepancy;Nuclear Fusion;2023-07-31
3. Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns;Nuclear Materials and Energy;2023-03
4. Fuel retention and carbon deposition on beryllium marker tiles from JET tokamak main chamber limiters investigated by ion beam analysis;Nuclear Fusion;2022-11-15
5. Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997;Nuclear Materials and Energy;2022-10
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