发明名称 Salzschmelze fuer Brutreaktoren
摘要 1,137,616. Cooling reactors. UNITED STATES ATOMIC ENERGY COMMISSION. 16 Oct., 1967 [25 Nov., 1966], No. 47032/67. Heading G6C. In a molten-salt-fuel, breeder nuclear reactor power plant, steam generation is effected in heat exchangers and the reactor coolant is a liquid salt. The fuel salt is separated from the blanket salt by graphite tubes and supercritical steam is generated in the exchangers. The fuel and blanket salts flow through separate heat exchangers. The secondary coolant, the liquid salt, flows first through the fuel heat exchanger and then through the blanket exchanger passing next to steam superheaters. The coolant salt may also be circulated through reheaters which heat a supply of steam for the intermediate pressure turbine. The fuel salt consists of uranium fluoride dissolved in the fluorides of 7-lithium and beryllium, the breeder material is a mixture of the fluorides of 7-lithium and thorium. The coolant salt is the mixture NaF - KF - BF 3 . The blanket gas in the coolant circuit may be BF 3 .
申请公布号 DE1614948(A1) 申请公布日期 1970.12.23
申请号 DE19671614948 申请日期 1967.11.23
申请人 UNITED STATES ATOMIC ENERGY COMMISSION 发明人 ELLIOTT THOMA JUN.,ROY;MCCOOK HEBERT,GORDON
分类号 C09K5/12;G21C15/28 主分类号 C09K5/12
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