JPS5814195U

JPS5814195U - Reactor containment vessel protection device

Info

Publication number: JPS5814195U
Application number: JP1981107834U
Authority: JP
Inventors: 寺坂　晴夫
Original assignee: 株式会社東芝
Priority date: 1981-07-22
Filing date: 1981-07-22
Publication date: 1983-01-28

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

[Brief explanation of the drawing]

第１図は従来の原子炉を部分的に示す縦断面図、第２図
は圧力配管の破断口からの距離と破断口からの噴出流に
よるジェット力との関係を示すグラフ、第３図は本考案
に係る原子炉格納容器保護装置を備えた原子炉を例示す
を縦断面図、第４図は本考案の原子炉格納容器保護装置
の具体例を示す一部縦断面図、第５図は本考案の原子炉
格納容器保護装置力具体例を示す斜視図、第６図は第４
図および第５図に示す装置の作用を説明するための説明
図、第７図は保護装置の設置の有無による原子炉格納容
器内壁に加わる圧力を示すグラフである。１・・・主蒸気管、２・・・原子炉格納容器、３・・・
原子炉圧力容器、４・・・破断口、５・・・コンクリー
ト遮へい壁、６・・・圧力抑制室、７・・・サプレッシ
ョンプール、８・・・ペンドパイプ、９・・・密閉空間
、１０・・・給水管、１１・・・炉心部、１２・・・遮
断弁、１３・・・主蒸気隔離弁、１４・・・再循環系、
１５・・・再循環ポンプ、１６・・・吸込側配管、１．
７・・・吐出側配管、１８・・・保護装置、１９・・・
噴霧口、２０・・・分岐配管、２１・・・供給配管、２
２・・・加圧容器、２３・・・圧力検出器、２４・・・
作動弁、−２５・・・制御回路、２６・・・緩衝材。Figure 1 is a vertical cross-sectional view partially showing a conventional nuclear reactor, Figure 2 is a graph showing the relationship between the distance from the rupture port of the pressure piping and the jet force due to the jet flow from the rupture port, and Figure 3 is FIG. 4 is a longitudinal cross-sectional view illustrating a nuclear reactor equipped with a reactor containment vessel protection device according to the present invention; FIG. 4 is a partial vertical cross-sectional view showing a specific example of the reactor containment vessel protection device according to the present invention; FIG. 6 is a perspective view showing a concrete example of the power of the reactor containment vessel protection device of the present invention, and FIG.
FIG. 7 is a graph showing the pressure applied to the inner wall of the reactor containment vessel depending on whether a protection device is installed or not. 1... Main steam pipe, 2... Reactor containment vessel, 3...
Reactor pressure vessel, 4... Break port, 5... Concrete shielding wall, 6... Pressure suppression chamber, 7... Suppression pool, 8... Pend pipe, 9... Closed space, 10. ... Water supply pipe, 11 ... Core part, 12 ... Shutoff valve, 13 ... Main steam isolation valve, 14 ... Recirculation system,
15... Recirculation pump, 16... Suction side piping, 1.
7...Discharge side piping, 18...Protective device, 19...
Spray port, 20... Branch pipe, 21... Supply pipe, 2
2... Pressurized container, 23... Pressure detector, 24...
Operating valve, -25...Control circuit, 26...Buffer material.

Claims

[Claims for Utility Model Registration] 1. A buffer solution spraying device is provided on the inner wall of the reactor containment vessel to which high pressure pipes connected to the reactor pressure vessel are connected, which sprays a buffer solution when the high pressure pipes are ruptured. A reactor containment vessel protection device characterized by comprising: 2. A buffer solution spraying device includes a plurality of branch pipes having a large number of spray ports for spraying a buffer solution, a supply pipe that supplies the buffer solution to these branch pipes, a pressurized container that stores the buffer solution, and an atom It is characterized by comprising a pressure detector installed on the inner wall of the reactor containment vessel, and a control circuit that drives an operating valve provided between the pressurized vessel and the supply pipe based on the pressure detected by the pressure detector. A nuclear reactor containment vessel protection device according to claim 1 of the utility model registration claim. 3. A utility model characterized in that the spray nozzle installed in the branch pipe is deflected slightly above horizontal to increase the flight distance of the buffer solution and to increase the efficiency of condensing water vapor ejected from the high-pressure pipe. A reactor containment vessel protection device according to registered claim 2.