U.S. Solid Breeder Blanket Design for ITER

Integrated 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...

Tritium 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...

An 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...

US Plans and Strategy for ITER Blanket Testing

Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER from Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation in the ITER Test Blanket Module (TBM) ...

UWFDM-1257 US Plans and Strategy for ITER Blanket Testing