首页> 外国专利> Sodium cooling circuit for nuclear reactor - where sodium heats steam generator, and is pumped through circuit contg. de-surging reservoir and gas equalising sodium pressure

Sodium cooling circuit for nuclear reactor - where sodium heats steam generator, and is pumped through circuit contg. de-surging reservoir and gas equalising sodium pressure

机译:核反应堆的钠冷却回路-钠加热蒸汽发生器,并泵送通过回路contg。使油层反跳并使气体均衡钠压

摘要

Parent patent describes heat transfer from a reactor to a steam generator (6) via liq. sodium. The bottom end of the Na outlet pipe (6b) on generator (6) enters a reservoir (24) provided with an electromagnetic pump. The novelty in this addn. is that the electromagnetic pump is replaced by a mechanical pump (12"), with a free liq. level, mounted above reservoir (24) on a branch pipe (12"b) on pipe (6b). The outlet of pump (12") is directly connected to an intermediate heat exchanger. The pump outlet pipe is pref. fitted with a gas escape vent; and an equiv. amt. of gas is fed by a pipe into reservoir (24). The Na does not circulate through reservoir (24), but flows directly to pump (12"); and reservoir (24) functions as a desurger, eliminating "liq. hammer".
机译:母专利描述了通过液面从反应器到蒸汽发生器(6)的热传递。钠。发生器(6)上的Na出口管(6b)的底端进入装有电磁泵的储液器(24)。这个插件的新颖性。电磁泵由具有自由液位的机械泵(12“)代替,该机械泵安装在容器(6b)上的支管(12” b)的储液罐(24)上方。泵(12“)的出口直接连接到中间热交换器。泵的出口管预装有排气口;通过管道将等量的天然气供入储液器(24)。 Na不循环通过储液器(24),而是直接流向泵(12“);储存器(24)起到去油器的作用,消除了“液锤”。

著录项

  • 公开/公告号FR2474744B2

    专利类型

  • 公开/公告日1983-06-03

    原文格式PDF

  • 申请/专利权人 ELECTRICITE DE FRANCE;

    申请/专利号FR19800001616

  • 发明设计人

    申请日1980-01-25

  • 分类号G21D5/08;G21D1/04;F16J15/16;

  • 国家 FR

  • 入库时间 2022-08-22 10:01:24

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