Title of article
Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMO
Author/Authors
Poitevin، نويسنده , , Y. and Boccaccini، نويسنده , , L.V. and Zmitko، نويسنده , , M. and Ricapito، نويسنده , , I. and Salavy، نويسنده , , J.-F. and Diegele، نويسنده , , Douglas E. and Gabriel، نويسنده , , F. and Magnani، نويسنده , , E. and Neuberger، نويسنده , , H. and Lنsser، نويسنده , , R. and Guerrini، نويسنده , , L.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2010
Pages
8
From page
2340
To page
2347
Abstract
Europe has developed two reference tritium breeder blankets concepts that will be tested in ITER under the form of Test Blanket Modules: (i) the Helium-Cooled Lithium–Lead which uses the liquid Pb–15.7Li as both breeder and neutron multiplier, (ii) the Helium-Cooled Pebble-Bed with lithiated ceramic pebbles as breeder and beryllium pebbles as neutron multiplier.
ensive development program has been carried-out over the last decade combining experimental and numerical simulations aimed at identifying and quantifying physical phenomena occurring in breeder blankets and at optimizing their design and technologies accordingly. On this basis, sound guidelines for the design and technological choices of Test Blanket Modules can be derived. In addition, regulatory and ITER project requirements, which prefigure the future DEMO blanket ones, are now integrated in the development and qualification program of the Test Blanket Modules. Their scope and implication are analyzed.
Keywords
TBM , Demo , Breeder Blanket , Design , technology
Journal title
Fusion Engineering and Design
Serial Year
2010
Journal title
Fusion Engineering and Design
Record number
2357344
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