Neutronics and Thermal Design Analyses of U.S. Solid Breeder Blanket for ITER
نویسندگان
چکیده
منابع مشابه
UWFDM-839 Three-Dimensional Neutronics Analysis of the US Blanket Design for ITER
Detailed three-dimensional neutronics analysis has been performed for ITER with the U.S. solid breeder blanket utilizing sintered product materials for both the breeder and multiplier. The overall tritium breeding ratio is 0.81 with two outboard breeder zones and 0.89 for the three outboard breeder zone design option. The total reactor thermal power is 1150 MW in the technology phase.
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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...
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An In-depth analysis of the INT05 tritium-production—blanket design Is presented. A ternary system of solid silicate breeder, lead neutron multiplier, and graphite moderator is explored primarily from safety and blanket tritium-inventory considerations. Lithiumsilicate (Li2Si03) bleeder systems are studied along 2 with water (H2P/D2O) and Type 316 stainless steel as coolant and structural mater...
متن کاملAn overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design
An attractive blanket concept for the fusion reactor is the dual coolant Pb–17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb–17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetoh...
متن کاملTritium Analysis of a Water-cooled Solid Breeder Blanket for Iter*
Mass, (lo6 g) Volume, (m3) Thickness, (cm) T. Gen. Rate, (g/day) Abstract: This paper presents quantitative predict,ions for the tritium release and inventory in a water-cooled solid breeder blanket for the International Thermonuclear Experimental Reactor (ITER) obtained from the tritium transport code MISTRAL [l] recently developed at UCLA. The blanket consists of a layout assembly of solid br...
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ژورنال
عنوان ژورنال: Fusion Technology
سال: 1991
ISSN: 0748-1896
DOI: 10.13182/fst91-a29546