Re-evaluation of the impact of wall retention on Tritium-self-sufficiency in fusion reactors
In recent years several publications have claimed that the retention of tritium (T) in the first wall armor material poses a limitation on when a fusion reactor becomes T-self-sufficient. While the prediction on wall retention therein are correct, the model applied to assess the T-self-sufficiency i...
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Main Author: | K. Schmid |
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Format: | Article |
Language: | English |
Published: |
IOP Publishing
2025-01-01
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Series: | Nuclear Fusion |
Subjects: | |
Online Access: | https://doi.org/10.1088/1741-4326/ada458 |
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