منابع مشابه
Heat deposition, damage, and tritium breeding characteristics in thick liquid wall blanket concepts
The advanced power extraction (APEX) study aims at exploring new and innovative blanket concepts that can efficiently extract power from fusion devices with high neutron wall load. Among the concepts under investigation is the free liquid FW/liquid blanket concept in which a fast flowing liquid FW ( 2–3 cm) is followed by thick flowing blanket (B) of 40–50 cm thickness with minimal amount of st...
متن کاملTritium Modeling for Iter Test Blanket Module
HCPB (Helium Cooled Pebbles Bed) Test Blanket Model (TBM) is based on solid breeder. Tritium has to be extracted using Helium purge gas flowing through breeder pebbles bed. He-stream must be cooled down and processed and all these steps are carried out in TES (Tritium Extraction System). A modeling work has been performed to study the behavior of the TES of the HCPB TBM and for Molecular Sieve ...
متن کاملModeling of tritium release from beryllium in fusion blanket applications
Only limited data are available on tritium release from irradiated Be. Few models have been suggested for tritium release from beryllium. Simple diffusion/desorption models have been proposed, but lack the capability of accounting for important phenomena such as burst release through interconnected porosity and the effect of the Be0 impurity layer. This paper describes the application of a new ...
متن کاملTritium Transport in Poloidal Flows of a Dcll Blanket
In a Dual-Coolant Lead-Lithium (DCLL) blanket, tritium losses from the PbLi into cooling helium streams may occur when the liquid-metal breeder is moving in the poloidal ducts. Quantitative analysis of the mass transfer processes associated with the tritium transport in the breeder as well as tritium diffusion through the structural and functional materials is important for two main reasons. Th...
متن کاملUWFDM-837 Neutronics and Thermal Analyses for the Breeding Blanket of the ICF Tritium Production Reactor SIRIUS-T
A breeding blanket design for the tritium production ICF reactor SIRIUS-T is presented. The blanket consists of alternating layers of beryllium multiplier and lithium breeder/coolant with vanadium alloy structure. A tritium breeding ratio of 1.9 can be achieved for the optimum layered configuration with lithium enriched to 90% 6Li. An optimum coolant routing scheme is utilized to achieve adequa...
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ژورنال
عنوان ژورنال: Fusion Technology
سال: 1991
ISSN: 0748-1896
DOI: 10.13182/fst91-a29542