JPH0255197U

JPH0255197U -

Info

Publication number: JPH0255197U
Application number: JP1988133235U
Authority: JP
Priority date: 1988-10-12
Filing date: 1988-10-12
Publication date: 1990-04-20

Description

[Brief explanation of drawings]

第１図ないし第５図は本考案の原子炉格納容器
の実施例を示すものである。第１図は第一実施例
（請求項１）を示す要部の縦断面図、第２図は第
二実施例（請求項２）を示す要部の縦断面図、第
３図は第三実施例（請求項３）を示す要部の縦断
面図、第４図および第５図は第四実施例（請求項
４）を示すものであり、第４図は要部の斜視図、
第５図は要部の縦断面図、第６図および第７図は
従来の原子炉格納容器の一例を示すものであり、
第６図は一部を省略した縦断面図、第７図は第６
図におけるＸ円部の拡大図である。１……コンクリート壁、２ａ……底部ライナ、
３……鋼製容器壁、１１……サンドクツシヨン、
２０……採集管（パイプ）、２３……素子保護管
（パイプ）、２４……湿度センサ、２６……金網
、２７……空間部、２８……パイプ、３０……フ
アイバスコープ（カメラ）、３５……チヤンネル
、３５ａ……小孔、３６……空間部、３８……フ
アイバスコープ（カメラ）。 1 to 5 show an embodiment of the reactor containment vessel of the present invention. Fig. 1 is a vertical sectional view of the main part showing the first embodiment (Claim 1), Fig. 2 is a longitudinal sectional view of the main part showing the second embodiment (Claim 2), and Fig. 3 is a longitudinal sectional view of the main part showing the second embodiment (Claim 2). FIG. 4 and FIG. 5 are longitudinal cross-sectional views of the main parts showing the embodiment (claim 3), FIG. 4 is a perspective view of the main parts, and FIG.
FIG. 5 is a vertical cross-sectional view of the main parts, and FIGS. 6 and 7 show an example of a conventional reactor containment vessel.
Figure 6 is a partially omitted vertical cross-sectional view, Figure 7 is the 6th cross-sectional view.
It is an enlarged view of the X circle part in the figure. 1... Concrete wall, 2a... Bottom liner,
3...Steel container wall, 11...Sand cushion,
20... Collection tube (pipe), 23... Element protection tube (pipe), 24... Humidity sensor, 26... Wire mesh, 27... Space section, 28... Pipe, 30... Fiberscope (camera), 35...Channel, 35a...Small hole, 36...Space, 38...Fiber scope (camera).

Claims

[Claims for Utility Model Registration] (1) A concrete wall surrounding the steel container wall is provided on the outside of the steel container wall with a space between the steel container wall and the steel container wall. In a reactor containment vessel in which a sand cushion made of sand-like particles is provided between a lower end portion and a lower end portion of the concrete wall, the upper end portion is opened inside the sand cushion and outside the sand cushion. A nuclear reactor containment vessel, characterized in that a pipe is inserted through the pipe whose lower end opens into the bottom of the sand cushion. (2) The reactor containment vessel according to claim 1, characterized in that a humidity sensor is provided in the pipe to measure the degree of dryness at the bottom of the sand cushion. (3) Provide a space in the sand cushion near the weld between the body of the steel container wall and the bottom liner, which is partitioned by a net and exposes the weld and its vicinity; 2. The reactor containment vessel according to claim 1, wherein a camera or a sensor is provided in the pipe, the tip of which moves freely in the space. (4) A concrete wall surrounding the steel container wall is provided on the outside of the steel container wall with a space between the steel container wall and the lower end of the steel container wall and the concrete wall. In a reactor containment vessel in which a sand cushion made of sand-like particles is provided between the lower end and the lower end, a large number of small holes are formed in the sand cushion, extending in the vertical direction and penetrating in the thickness direction. a transparent channel having both longitudinal edges in contact with the steel container wall and an upper end protruding from the upper surface of the sand cushion, and the steel container wall and the channel A nuclear reactor containment vessel characterized in that a camera or a sensor is provided in a space partitioned by.