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Differences in materials and construction of the four breeder blanket concepts lead to differing nuclear responses.
Comparisons are made between the waste-class masses generated for different tritium breeding blanket concepts.
Therefore, the selection of blanket concepts depends on the overall strategy for fusion power plant development.
ITER organization is providing an opportunity to the partner countries to test their breeding blanket concepts.
Performance of these functional materials will significantly impact the performance of respective blanket concepts.
Solid breeder and liquid breeder blanket concepts are being developed for testing in ITER.
SiC is the primary candidate for the flow channel inserts in dual-coolant blanket concepts.
Typical examples of candidate blanket concepts are compared in this study.
Li2TiO3 is regarded as a promising candidate breeder in solid blanket concepts.
A series of LiPb breeder blanket concepts were proposed for different applications of fusion in China.
The inclusion of such design modifications results in a significant reduction of the TBR for different breeder blanket concepts.
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