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An aqueous lithium salt blanket option for fusion power reactors

Don Steiner, Georgios Varsamis, Lowell Deutsch, John Rathke, Paul Gierszewski1989年Fusion Engineering and DesignIF 1.7出版社

An aqueous lithium salt blanket (ALSB) concept is proposed which could be the basis for either a power reactor blanket or a test module in an engineering test reactor. The design is based on an austenitic stainless steel structure, a beryllium multiplier, and a salt breeder concentration of about 32 g LiNO3 per 100 cm3 of H2O. To limit tritium release rates, the salt breeder solution is separated from the water coolant circuit. The overall tritium system cost for a 2400 MW (fusion power) reactor is estimated to be 180 million $ US87 installed.

日本語訳

水性リチウム塩ブランケット(ALSB)概念が提案され、これは動力炉または工学試験炉における試験モジュールのいずれかの基礎となり得る。本設計は、オーステナイト系ステンレス鋼構造、ベリリウム増倍材、および水100 cm3あたり約32 gのLiNO3濃度の塩増殖材に基づく。トリチウム放出率を制限するため、塩増殖溶液は水冷却回路から分離されている。2400 MW(核融合出力)の炉に対する全トリチウムシステムコストは、設置費として1億8000万米ドル(1987年価格)と見積もられる。

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