Global depletion analysis of Korean helium cooled solid breeder TBM model for demo fusion reactor

• Published in: Fusion engineering and design Vol. 85; no. 10; pp. 2222 - 2226
• Main Authors: Yun, Sunghwan, Cho, Nam Zin, Ahn, Mu-Young, Cho, Seungyon
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01-12-2010; Elsevier
• Subjects: Applied sciences; Beryllium; Ceramics; Controled nuclear fusion plants; Depletion; Depletion calculation; Design engineering; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fusion reactors; Graphite; Helium cooled; Helium cooled solid breeder (HCSB); Installations for energy generation and conversion: thermal and electrical energy; Lithium; Monte Carlo; MONTEBURNS code; Reflectors; Helium cooled solid breeder (HCSB); MONTEBURNS code; Monte Carlo; Depletion calculation; Breeder; Lithium; Tritium; Boundary condition; Helium; Nuclear fusion reactor; Blanket; Depletion; Beryllium; Graphite; Transmutation; Ceramic materials
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2010.08.042

The Korean HCSB (helium cooled solid breeder) TBM (test blanket module) is proposed with its specific compositions of lithium ceramic, beryllium and graphite in pebble form. In the Korean HCSB TBM, the amount of beryllium is reduced and the reduction is replaced by graphite for a neutron reflector, while tritium breeding ratio (TBR) remains almost unchanged with relatively low Li
6 enrichment of ∼40%. However, the previous Korean HCSB was designed based on the LOCAL assumption, in which the surroundings are assumed by the reflective boundary condition. In this research, we establish a simple GLOBAL neutronics model based on demo fusion reactor and perform neutronics analyses including depletion (transmutation) calculation during 100 EFPDs (effective full power days) using the modified MONTEBURNS code.