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Tritium recycling, permeation and inventory in a self-cooled fusion reactor blanket using Pb17Li or Flibe as a breeder and V or Fe as a first wall material

✍ Scribed by G Gervasini; F Reiter


Publisher
Elsevier Science
Year
1989
Tongue
English
Weight
282 KB
Volume
39
Category
Article
ISSN
0042-207X

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