UWFDM-813 An Aqueous Lithium Salt Blanket for ITER
نویسنده
چکیده
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 determined from 3-D neutronics calculations is 0.88. The aqueous salt flow parameters have been optimized to minimize the salt pressure and inventory leading to a pressure of 1.15 MPa and tritium inventory of 104 g. There are no crevices in the aqueous salt channels and a redundancy has been provided against a salt to water leak potential. The first wall, blanket, and shield qualify for shallow land burial. The highest temperature in the blanket after a two week period without coolant is only 440°C. The first wall and blanket are capable of withstanding the worst disruption load.
منابع مشابه
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