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Mechanism of the safety dropout

机译:安全退出机制

摘要

872,092. Controlling reactors. NUCLEAR POWER PLANT CO. Ltd. Aug. 14, 1959 [Sept. 8, 1958], No. 28768/58. Class 39(4). A safety release mechanism for releasing a member from a parent member in response to changes in pressure in a fluid in which the releasable member is immersed comprises a push rod attached to the releasable member and operable to trip a latch mechanism joining the releasable member to the parent member and a pressure sensitive device located in the releasable member and forming an enclosed space therein; the pressure sensitive device being responsive to pressure changes between the enclosed space and fluid surrounding the releasable member and exerting a force on the push rod sufficient to trip the latch mechanism when a predetermined pressure change occurs. Fig. 1 shows an arrangement for releasing a control or safety rod in a gascooled nuclear reactor. The control rod comprises a tube 2 containing boron and arranged between inner and outer stainless steel tubes 1, 3. The outer tube 1 is welded to a tube 21 attached to a lifting head 13. A bellows 6 provided with an orifice 9 forms an enclosed chamber within the control rod so that if the gas pressure outside the rod falls, the bellows expand pushing up push rods 10 which act on a plate 15 and a further push rod 14 to actuate a latch mechanism and release the control rod. If the temperature of the gas around the control rod rises excessively tube 21 expands thus causing an end cap 11 to press down on the ends of levers 26 which push up the rods 10 and release the control rod. To retrieve the rod from the reactor the member 20 is lowered by a rope or chain until it contacts the top of the rod where, due to the geometry of the system, the pawls 24 under the weight of member 20 are rotated into the locking position by cam action of the pawls 24 on the inclined faces of lifting head 13.
机译:872,092。控制反应堆。核动力厂有限公司1959年8月14日[9月[1958年8月8日],第28768/58号。 39(4)类。一种安全释放机构,该安全释放机构用于响应于将可释放构件浸入其中的流体中的压力变化而从母体构件释放构件,该安全释放机构包括推杆,该推杆附接到该可释放构件,并且可操作以使将可释放构件连接至可释放构件的闩锁机构跳闸。母部件和位于可释放部件中并在其中形成封闭空间的压敏装置。压敏装置响应于封闭空间和围绕可释放构件的流体之间的压力变化,并且在发生预定压力变化时在推杆上施加足以使闩锁机构跳闸的力。图1示出了用于释放气冷核反应堆中的控制棒或安全棒的装置。控制杆包括一根管子2,管子中装有硼,管子2布置在内部和外部不锈钢管1、3之间。外部管子1焊接到与提升头13相连的管子21上。波纹管6上有一个孔9,形成一个封闭的在控制杆内的腔室中,如果波纹管外部的气压下降,则波纹管会膨胀,推起推杆10,推杆10作用在板15上,另一推杆14致动闩锁机构并释放控制杆。如果控制杆周围的气体温度过度升高,则管21膨胀,从而导致端盖11向下压在操纵杆26的两端,从而推动杆10并释放控制杆。为了从反应器中取回杆,构件20通过绳索或链条降低,直到其接触杆的顶部,由于系统的几何形状,在构件20的重量下,棘爪24旋转到锁定位置通过棘爪24在提升头13的倾斜面上的凸轮作用。

著录项

  • 公开/公告号FR1234552A

    专利类型

  • 公开/公告日1960-10-18

    原文格式PDF

  • 申请/专利号FR19590804228

  • 发明设计人

    申请日1959-09-03

  • 分类号G21C7/12;G21C9/02;G21C9/027;G21C19/10;G21C19/105;

  • 国家 FR

  • 入库时间 2022-08-23 19:08:55

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