UWFDM-1257 US Plans and Strategy for ITER Blanket Testing
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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) ...
متن کاملUWFDM-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.
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.
متن کاملAn 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-813 An Aqueous Lithium Salt Blanket for ITER
An aqueous lithium salt blanket is designed as a candidate for the tritium production blanket of ITER. There are two rows of flat tube aqueous salt flow channels placed between beryllium blocks. The inboard and outboard blanket configurations have been optimized to maximize tritium breeding. A local outboard TBR of 1.44 is obtained using LiOH at a concentration of 5 g/100 cm3. The overall TBR d...
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