UWFDM-1327 Neutronics Analysis of a Molten Salt Blanket for the HAPL Laser Fusion Power Plant with Magnetic Intervention
نویسندگان
چکیده
A blanket concept made of SiCf/SiC composite and utilizing Flibe as coolant and tritium breeder has been developed and integrated with the magnetic intervention system. To achieve tritium self-sufficiency, a 1 cm thick Be insert is utilized in the first wall coolant channel. All magnet, vacuum vessel, and personnel shielding requirements can be satisfied. The nuclear performance parameters of this blanket were compared to those of a lithium-lead blanket in two chamber core configurations. Because of the lighter blanket and shield weight that needs to be supported, the higher thermal power, and the lower electrical conductivity, the Flibe blanket option is particularly well suited for a laser fusion power plant with magnetic intervention. Keywords-neutronics; laser fusion; magnetic intervention; nuclear heating; shielding
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UWFDM-1234 Neutronics Assessment of Molten Salt Breeding Blanket Design Options
DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government, nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclos...
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