发明名称 Process for Sodium Heated Modules
摘要 1,161,654. Nuclear power plant. UNITED STATES ATOMIC ENERGY COMMISSION. 14 March, 1968 [19 May, 1967], No. 12568/68. Heading G6C. In a nuclear reactor power plant, the turbine steam circuit and the reactor sodium coolant circuit are thermally coupled by a secondary sodium system. The turbines 21, 26 receive steam from the superheater 7 and reheater 8 which are themselves heated by a sodium flow from the intermediate heat exchanger 4. The latter receives heat from the coolant sodium of reactor 1 through the lines 2, 3. The secondary sodium flow in the lines 5, 6 is controlled by the valve 27 and pump 28 so that half the temperature drop occurs across 7, 8 and half across the evaporator 15. Thus, ordinary stainless steel may be used for the evaporator and chromium stainless steel for 7 and 8.
申请公布号 GB1161654(A) 申请公布日期 1969.08.20
申请号 GB19680012568 申请日期 1968.03.14
申请人 UNITED STATES ATOMIC ENERGY COMMISSION 发明人
分类号 G21D5/08 主分类号 G21D5/08
代理机构 代理人
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