Basic concepts of DEMO and a design of a helium-cooled molten lithium blanket for a testing in ITER

• Published in: Fusion engineering and design Vol. 82; no. 15; pp. 2399 - 2405
• Main Authors: Hong, Bong Geun, Lee, Dong Won, Wang, Son Jong, Kim, Yonghee, In, Wang Ki, Yoon, Kyung Ho
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.10.2007; New York, NY Elsevier Science
• Subjects: Applied sciences; Controled nuclear fusion plants; DEMO; Energy; Energy. Thermal use of fuels; Exact sciences and technology; HCML; Installations for energy generation and conversion: thermal and electrical energy; ITER; TBM; ITER; HCML; DEMO; TBM; Tokamak; Plasma; Breeder; Coolant; Computational fluid dynamics; Divertor; Lithium; Tritium; Shielding; Helium; Nuclear fusion reactor; Blanket; Graphite; Thermohydraulics; Ferritic steel
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2007.04.046

Basic concepts and the performance of DEMO for an early realization have been investigated with a limited extension of its plasma physics and technology from the second phase of the International Thermonuclear Experimental Reactor (ITER) operation (EPP phase). With the same plasma size as that of ITER, net electric power up to 600 MW is possible with β N > 4.0, H > 1.0 and a divertor heat load of H div < 15 MW/m 2. Through a consideration of the requirements for a DEMO-relevant blanket concept, Korea has proposed a He cooled molten lithium (HCML) blanket as an ITER TBM. It uses He as a coolant and Li is used as a tritium breeder by considering its potential advantages. Low activation Ferritic Steel (FS) is used as a structural material and two layers of graphite are inserted as a reflector in the breeder zone to increase the tritium breeding ratio (TBR) and the shielding performances. The design and the performance of the KO HCML test blanket module (TBM) are being modified in terms of its He coolant efficiency and its optimized path with a performance analysis; with a 3D Monte Carlo analysis (MCCARD code) for the neutronics; with the CFD code (CFX-10) for the thermal-hydraulics; with ANSYS-10 for the thermo-mechanical analysis.