The Helium-Cooled Lithium Lead (HCLL) and Water-Cooled Lithium Lead (WCLL) Breeding Blankets are two of the four blanket designs proposed for DEMO reactor. The study of tritium transport inside the blankets is fundamental to assess their preliminary design and safety features. A mathematical model has been derived, in a new form making makes easier to determine the most critical components as far as tritium losses and tritium inventories are concerned, and to model the tritium performance of the whole system. Two cases have been studied, the former with tritium generation rate constant in time and the latter considering a typical pulsed operation for a time span of 100 h. Tritium inventories and tritium losses are the main output of the model. Tritium concentrations, inventories and losses are initially calculated and compared for the two blankets, in a reference case without permeation barriers or cold traps. A parametric study to show the behavior of the two systems when certain parameters are changed, in order to minimize inventories and/or losses, has been carried out.
Tritium transport in HCLL and WCLL DEMO blankets / Candido, Luigi; Utili, Marco; Nicolotti, Iuri; Zucchetti, Massimo. - In: FUSION ENGINEERING AND DESIGN. - ISSN 0920-3796. - STAMPA. - 109-111:A(2016), pp. 248-254. [10.1016/j.fusengdes.2016.03.017]
|Titolo:||Tritium transport in HCLL and WCLL DEMO blankets|
|Data di pubblicazione:||2016|
|Digital Object Identifier (DOI):||http://dx.doi.org/10.1016/j.fusengdes.2016.03.017|
|Appare nelle tipologie:||1.1 Articolo in rivista|
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