Article ID Journal Published Year Pages File Type
273065 Fusion Engineering and Design 2008 5 Pages PDF
Abstract

Through a consideration of the requirements for a DEMO-relevant blanket concept, Korea (KO) has proposed a He cooled molten lithium (HCML) blanket with ferritic steel (FS) as a structural material in the International Thermonuclear Experimental Reactor (ITER) program. The design and the performance of the KO HCML test blanket module (TBM) and the preliminary results of the safety analyses such as activation, decay heat, and accident analysis by a loss of coolant are introduced briefly in this paper. KO HCML TBM uses He as a coolant and Li is used as a tritium breeder by considering its potential advantages. Two layers of graphite are inserted as a reflector in the breeder zone to increase the tritium breeding ratio (TBR) and the shielding performances. Performance analyses were performed with the MCCARD code for the neutronics, the CFX-10 code for the thermal–hydraulics, and with the ANSYS-10 code for the thermal–mechanical analysis. For the safety analyses, the activation and decay heat were obtained from the MCCARD and Origen codes. From the obtained decay heat, an accident analysis was performed.

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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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