Materials science problems of blankets in Russian concept of fusion reactor

Structural materials, beryllium and tritium breeding materials proposed for blanket of Russian reactor DEMO and Test Modules for ITER are discussed. Main requirements for the materials are concerned with basis current designs of blankets and modules and possibility meet of ones for presence and deve...

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Bibliographic Details
Published inJournal of nuclear materials Vol. 258; pp. 30 - 46
Main Author Solonin, M.I
Format Journal Article
LanguageEnglish
Published Elsevier B.V 01.10.1998
Subjects
S06
B10
B02
B04
V01
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Summary:Structural materials, beryllium and tritium breeding materials proposed for blanket of Russian reactor DEMO and Test Modules for ITER are discussed. Main requirements for the materials are concerned with basis current designs of blankets and modules and possibility meet of ones for presence and developed alloys and materials discussed considered. Main properties and results of test of ferrite-martensite and vanadium alloys for DEMO and Test Modules are cited. Beryllium compositions used as component of First Wall and neutron multiplier are discussed. Liquid lithium and ceramic (lithium orthosilicate) are treated as tritium breeding materials. Russian development of reactor experimental unit for tritium breeding zone using beryllium, lithium ceramic and ferrite-martensite alloys for structural materials is presented.
Bibliography:SourceType-Scholarly Journals-2
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ISSN:0022-3115
1873-4820
DOI:10.1016/S0022-3115(98)00353-5