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the limiter body escape for foundations of fuel elements of nuclear reactors

机译:核反应堆燃料元件基础的限位器逃逸

摘要

1463532 Nuclear reactors SOC GENERALE DE CONSTRUCTIONS ELECTRIQUES ET MECANIQUES ALSTHOM 20 March 1974 [22 March 1973] 12474/74 Heading G6C In a nuclear reactor cooled by a liquid, fuel elements are carried by a support plate which has recesses each accommodating the foot of a respective fuel element, the foot defining an internal flow passage for the liquid and having a region of reduced cross-sectional flow area, this region being in communication with the space between the foot and the wall of the associated recess at a position downstream of a labyrinth seal acting between the foot and the wall. Thus, any leakage coolant in the space can enter the foot by virtue of the reduced static pressure in the region of reduced flow area. In one embodiment (Fig. 1) the foot 3 is centred in the recess 2 of support plate 1 by partspherical protuberances 5; intermediate its length, the foot 3 affords seals 8, 13 for reducing leakage flow in the space 12. Downstream of the seal 8, orifices 11 connect the space 12 with the flow channel within the foot 3 in the region of a narrowed portion 10 of the channel. By conducting leakage flow from space 12 into the flow channel in the foot, leakage flow past the protuberances 5 is minimized. Pressure in space 12 is maintained higher than in space 15 above support plate 1 so as to preclude reverse leakage past protuberances 5. The effects of this pressure differential are minimized by the further seal 13. In a second embodiment (Fig. 2) the foot is centred by means of an annular rib 16 which also acts as a seal; the further labyrinth seal is dispensed with. In a third embodiment (not shown), similar to that of Fig. 2, the further labyrinth seal, such as is provided in the embodiment of Fig. 1, is included. In a fourth embodiment (Fig. 4) the crosssectional flow area of the channel within the foot is reduced by means of an internal structure comprising diaphragms 18. The orifices 11 are provided in the vicinity of one such diaphragm. Levitation of the fuel element by the coolant pressure is minimized by providing for lateral entry of coolant to the foot via apertures 14, 19.
机译:1463532核反应堆1974年3月20日[1973年3月22日]阿尔及利亚建筑电气总公司,第12474/74号G6C标题在由液体冷却的核反应堆中,燃料元件由支撑板承载,支撑板各有一个凹座,每个凹座可容纳相应的燃料元件,底脚限定用于液体的内部流动通道,并具有减小的横截面流动面积的区域,该区域在底脚下游的位置与底脚和相关凹口的壁之间的空间连通。迷宫密封在脚和墙壁之间起作用。因此,空间中任何泄漏的冷却剂可通过减小的流动面积区域中的减小的静压而进入脚部。在一个实施例中(图1),脚3通过部分球形的突起5在支撑板1的凹口2中居中;在图1中,脚3通过球形突起5居中。支脚3在其长度的中间提供密封件8、13,以减少空间12中的泄漏流。在密封件8的下游,孔11在支脚3的狭窄部分10的区域中将空间12与支脚3内的流动通道连接。这个频道。通过将泄漏空间从空间12引导到脚中的流动通道中,使通过突起5的泄漏流最小化。保持空间12中的压力高于支撑板1上方的空间15中的压力,以防止通过突起5的反向泄漏。通过另外的密封件13使该压差的影响最小化。在第二实施例中(图2),脚通过环形肋16居中,该环形肋也用作密封件。不再需要迷宫式密封。在第三实施例(未示出)中,类似于图2的实施例,还包括诸如在图1的实施例中提供的另一迷宫式密封件。在第四实施例(图4)中,通过包括隔膜18的内部结构减小了脚内的通道的横截面流通面积。在一个这样的隔膜附近设置孔11。通过使冷却剂通过孔14、19横向进入脚,使冷却剂压力对燃料元件的悬浮作用最小化。

著录项

  • 公开/公告号IT1007613B

    专利类型

  • 公开/公告日1976-10-30

    原文格式PDF

  • 申请/专利号IT19740020539

  • 发明设计人

    申请日1974-04-08

  • 分类号G21C;

  • 国家 IT

  • 入库时间 2022-08-23 02:39:24

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