منابع مشابه
An overview of US ITER test blanket module program
A testing strategy and corresponding test plan have been presented for the two proposed US candidate breeder blankets: (1) a helium-cooled solid breeder concept with ferritic steel structure and Be neutron multiplier, but without a fully independent TBM and (2) a dual-coolant helium-cooled ferritic steel structure with self-cooled LiPb breeding zone that uses a flow channel insert as MHD and th...
متن کاملUWFDM-1395 Improvements to the Helium Flow Path in the US DCLL ITER Test Blanket Module
Computational fluid dynamics simulations have demonstrated flow problems within the helium flow path in the current US DCLL ITER test blanket module design. New geometry for the helium flow path has been designed that will improve flow evenness and simplify the overall helium flow path within the test blanket module while maintaining the overall test blanket module geometry. Global changes to t...
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 کاملIntegrated thermo-fluid analysis towards helium flow path design for an ITER solid breeder blanket module
The successful design and development of a complex system, like the ITER test blanket module (TBM) warrants the need f extensive computer aided engineering (CAE) activities. In this light, a sophisticated numerical flow solver (‘SC/Tetra’ by RADLE®), with a robust CAD interface, has been used to develop and evaluate helium coolant flow schemes for a solid breeder est blanket module design curre...
متن کاملUWFDM-1393 Two-Dimensional Nuclear Analysis in Support of ITER Blanket Module Design
Detailed profiles of nuclear heating and radiation damage parameters were determined in ITER blanket modules at different poloidal locations. The results indicate that the nuclear parameters are sensitive to the configuration and material composition with enhanced steel heating and helium production in regions with large water content.
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ژورنال
عنوان ژورنال: Fusion Technology
سال: 1996
ISSN: 0748-1896
DOI: 10.13182/fst96-a11962997