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Assembly of elements of the moderator solid for nuclear reactors.

机译:核反应堆缓和剂固体元件的组装。

摘要

913,887. Moderator structures. SOC. NATIONALE D'ETUDE ET DE CONSTRUCTION DE MOTEURS D'AVIATION. Dec. 1, 1960 [Dec. 4, 1959], No. 41381/60. Class 39 (4). A moderator structure for use in a high temperature nuclear reactor subjected to accelerations and to substantial inclinations to the vertical, e.g. a nuclear reactor used as the energy source for the propulsion of an aircraft, comprises an assembly of mutually independent moderator columns capable of expanding laterally by reason of clearances provided between adjacent columns and axially by reason of resilient guide means which also provide axial compression for giving mechanical cohesion to each column. In the embodiment shown, the columns comprise superposed elements 10, e.g. of beryllia, connected to each other by means of lugs 27. A tubular terminal member 13 at the upper end of each column embraces a sleeve 14 secured to the cover 2 of the reactor casing 1 while at the lower end of each column a terminal member 11 rests upon a support 12 secured to the lower part of the casing 1. The elements 10 in each column are pressed together by means of a helical spring 24 which abuts a shoulder 26 on the sleeve 14 to one end and a shoulder 25 on the member 13 at the other end. Longitudinal expansion is permitted by the members 13 sliding on the sleeves 14 and laterial expansion by the clearance 23 between adjacent columns. Coolant gas under pressure at a temperature around 350‹ C. enters the casing 1 through the inlet 5 and leaves at a temperature around 800‹ C. from the outlet 6, a deformable wall 7 separating the inlet zone from the outlet zone. Axial channels 15 are formed partly by central apertures in the elements 10, in which are housed fuel elements 20, and partly by bores 16 in the supports 12, bores 17 in the members 11, bores 18 in the members 13 and the bores 19 of the sleeves 14. Coolant gas enters the channels 15 through apertures 21 and leaves through apertures 22. The cover 2 is cooled by circulation of water by way of pipes 3, 4 and the casing 1 by immersion in protective water for the reactor.
机译:913,887。主持人结构。 SOC。全国建筑与发展博物馆。 1960年12月1日[ [1959年4月],编号41381/60。 39类(4)。在高温核反应堆中使用的减速器结构,会受到加速和相对于垂直方向(例如垂直方向)的明显倾斜。一种用作飞机动力的核反应堆,包括一个相互独立的减速器组件,该减速器组件由于在相邻的支柱之间设置有间隙而可横向扩展,并由于弹性的导向装置而可轴向扩展,该弹性的导向装置也可提供轴向压缩,从而机械凝聚力的每一列。在所示的实施例中,这些列包括叠加的元件10,例如叠置的元件10。 ,通过凸耳27彼此连接。在每列的上端的管状终端构件13包括固定在反应器壳体1的盖2上的套筒14,而在每列的下端,则是终端构件。 11上的支撑件固定在壳体1的下部。支撑件12固定在壳体1的下部。每一列中的元件10通过螺旋弹簧24压在一起,该弹簧紧靠在套筒14的一端的肩部26和一端的肩部25。另一端的成员13。通过在套筒14上滑动的构件13允许纵向膨胀,并且通过相邻列之间的间隙23允许横向膨胀。压力为350℃左右的冷却气体通过入口5进入壳体1,并以800℃左右的温度从出口6离开,可变形壁7将入口区域与出口区域分隔开。轴向通道15部分地由元件10中的中心孔形成,燃料元件20被容纳在其中,并且部分地由支撑件12中的孔16形成,构件11中的孔17,构件13中的孔18和构件13的孔19形成轴向通道15。冷却剂气体通过孔21进入通道15,并通过孔22离开。盖2通过水通过管道3、4和壳体1的循环冷却,方法是将其浸入反应器的保护水中。

著录项

  • 公开/公告号LU39474A1

    专利类型

  • 公开/公告日1961-01-30

    原文格式PDF

  • 申请/专利权人

    申请/专利号LUD39474

  • 发明设计人

    申请日1960-11-29

  • 分类号C08G8/28;G21C1/12;G21C5/04;

  • 国家 LU

  • 入库时间 2022-08-23 18:51:03

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