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Gas cooled reactor - with core and primary coolant circuit incorporated in concrete pressure vessel

机译:气冷堆-在混凝土压力容器中装有堆芯和主冷却剂回路

摘要

1314498 Reactor pressure vessels COMMISSARIAT A L'ENERGIE ATOMIQUE 5 April 1972 [9 April 1971 13 May 1971] 15689/72 Heading G6C A nuclear reactor installation comprises a prestressed concrete, axially vertical pressure vessel 1 an upper part of which has therein a main cavity 3 containing the reactor core 4, and a lower part of which, below the core, has vertical cavities 12 connected at their top ends to ;he main cavity and at their bottom ends with the bottom surface of the vessel, the vertical cavities serving to house thermal energy extraction apparatus. In the embodiment shown the cavities 12 have bottom plugs 13 located in a pit 14 beneath the pressure vessel which rests on radial bearing elements 14a. The disposition of the cavities 12 is such as to leave a central concrete block 15 below the main cavity. In another embodiment (Fig. 3, not shown), which utilizes spherical fue elements, the latter are discharged downwards from the core by a device (16) positioned in the central concrete block. In a further embodiment (Figs. 4 and 5, not shown), the reactor, which is a fast neutron reactor, has a thick neutron and heat shield (17) disposed around the core and at the periphery of the main cavity. The shield can be partly cooled by cold gas returning to the core. Fuel charging and discharging is conducted from the bottom of the main cavity by devices (18) disposed in the central concrete block. Some of the vertical cavities are of smaller size than others and receive auxiliary cooling devices. In another embodiment (Fig. 6, not shown) the lower part of the pressure vessel is of reduced diameter defining a shoulder (23) whereby the vessel rests on support structures (24). In general, the reactor coolant gas may be CO 2 or He. The reactor may be thermal (using prismatic or spherical fuel elements), fast or HTR. The thermal energy extraction apparatus may comprise heat exchangers &c. or gas turbines. The arrangement of the vertical cavities enables hot gas to pass downwards through the thermal energy extraction apparatus and cool gas to pass upwards around that apparatus and adjacent the pressure vessel wall before returning to the core. The vessel mounting arrangement is said to afford increased stability in earthquakes; the pit 14 facilitates maintenance of the apparatus in the cavities.
机译:1314498反应堆压力容器COMMISSARIAT A L'ENERGIE ATOMIQUE 1972年4月5日[1971年4月9日,1971年5月13日] 15689/72品目G6C核反应堆装置包括一个轴向轴向垂直的预应力混凝土压力容器1,其上部有一个主腔包含反应堆堆芯4的图3所示的堆芯,其下部在堆芯下方,具有垂直腔室12,该垂直腔室的顶端连接到主腔室,并且在其底端与容器的底表面连接,该垂直腔室用于房屋热能提取设备。在所示的实施例中,空腔12具有位于压力容器下方的凹坑14中的底部塞子13,该底部塞子13搁置在径向轴承元件14a上。空腔12的布置使得在主空腔下方留下中央混凝土块15。在另一实施例中(图3,未示出),它利用球形烟气元件,后者通过位于中央混凝土砌块中的装置(16)从岩心向下排出。在另一个实施例中(图4和5,未示出),该反应堆是快速中子反应堆,具有厚的中子和隔热板(17),该隔热板和隔热板(17)设置在堆芯周围和主腔的外围。屏蔽层可以通过返回芯体的冷气部分冷却。燃料的充放电是通过设置在中央混凝土砌块中的装置(18)从主腔的底部进行的。一些竖直腔的尺寸小于其他竖直腔,并容纳辅助冷却装置。在另一个实施例中(图6,未示出),压力容器的下部具有减小的直径,其限定了肩部(23),由此,该容器搁置在支撑结构(24)上。通常,反应堆冷却剂气体可以是CO 2或He。反应堆可以是热反应堆(使用棱柱形或球形燃料元件),快速反应堆或HTR。热能提取设备可以包括热交换器c。或燃气轮机。垂直腔的布置使热气体能够向下通过热能提取设备,而冷气体能够在返回到堆芯之前围绕该设备并靠近压力容器壁向上通过。据说该船的安装装置在地震中具有更高的稳定性。凹坑14有利于设备在空腔中的维护。

著录项

  • 公开/公告号FR2137095B2

    专利类型

  • 公开/公告日1974-03-22

    原文格式PDF

  • 申请/专利权人 COMMISSARIAT A ENERGIE ATOMIQUEFR;

    申请/专利号FR19710017310

  • 发明设计人

    申请日1971-05-13

  • 分类号G21C13/00;

  • 国家 FR

  • 入库时间 2022-08-23 05:16:21

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