JPH0521519B2 - - Google Patents

Info

Publication number
JPH0521519B2
JPH0521519B2 JP62169623A JP16962387A JPH0521519B2 JP H0521519 B2 JPH0521519 B2 JP H0521519B2 JP 62169623 A JP62169623 A JP 62169623A JP 16962387 A JP16962387 A JP 16962387A JP H0521519 B2 JPH0521519 B2 JP H0521519B2
Authority
JP
Japan
Prior art keywords
pressure
containment vessel
reactor containment
purge
filter
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
JP62169623A
Other languages
Japanese (ja)
Other versions
JPS6415695A (en
Inventor
Noboru Ikegame
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP62169623A priority Critical patent/JPS6415695A/en
Publication of JPS6415695A publication Critical patent/JPS6415695A/en
Publication of JPH0521519B2 publication Critical patent/JPH0521519B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は、原子力プラントにおける原子炉格納
容器の漏洩試験用高圧ガスの減圧装置に関するも
のである。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a high pressure gas decompression device for leakage testing of a reactor containment vessel in a nuclear power plant.

(従来の技術) 第2図は、従来の原子炉格納容器の漏洩試験用
高圧ガスの減圧装置の配管系統図を示す。同図に
おいて、原子炉格納容器1に一端を接続した配管
2は、中間にバタフライ弁3A,3B,3C,3
D、パージ排気フアン4、プレフイルタ6と高性
能粒子フイルタ7を収納した排気フイルタケーシ
ング5、原子炉建屋排気フアン8を接続し、他端
を主排気筒9に接続している。
(Prior Art) FIG. 2 shows a piping system diagram of a conventional high-pressure gas decompression device for leak testing of a reactor containment vessel. In the figure, piping 2 whose one end is connected to reactor containment vessel 1 has butterfly valves 3A, 3B, 3C, and 3 in the middle.
D, a purge exhaust fan 4, an exhaust filter casing 5 housing a prefilter 6 and a high-performance particle filter 7, a reactor building exhaust fan 8 are connected, and the other end is connected to a main exhaust stack 9.

周知のように、原子炉格納容器1の漏洩試験
は、建設中または定期検査毎に実施される。この
ときの高圧ガスの圧力は、3〜4Kg/cm2で行われ
るが、漏洩試験終了後には定常状態まで減圧する
必要がある。
As is well known, a leakage test of the reactor containment vessel 1 is performed during construction or every periodic inspection. The pressure of the high-pressure gas at this time is 3 to 4 kg/cm 2 , but it is necessary to reduce the pressure to a steady state after the leak test is completed.

そこで、漏洩試験後の減圧について説明する。
バタフライ弁3Bを閉じ、バタフライ弁3C,3
Dを全開とし、配管2に比較して非常に細いバタ
フライ弁3Aを徐々に開くと同時にパージ排気フ
アン4を運転して、原子炉格納容器1内の圧力を
減圧する。
Therefore, the pressure reduction after the leakage test will be explained.
Close the butterfly valve 3B and close the butterfly valves 3C, 3.
D is fully opened, the butterfly valve 3A, which is very thin compared to the pipe 2, is gradually opened and at the same time the purge exhaust fan 4 is operated to reduce the pressure inside the reactor containment vessel 1.

この場合、原子炉建屋排気フアン8は常に運転
しているから、パージ排気フアン4を通つた排気
ガスは、プレフイルタ6や高性能粒子フイルタ7
を通過してダスト等を除去され、主排気筒9から
大気へ放出される。
In this case, since the reactor building exhaust fan 8 is always operating, the exhaust gas that has passed through the purge exhaust fan 4 is passed through the prefilter 6 and the high performance particle filter 7.
After passing through the air, dust and the like are removed, and the air is discharged into the atmosphere from the main exhaust stack 9.

(発明が解決しようとする問題点) しかしながら、バタフライ弁3Aの開度設定
は、原子炉格納容器1内の圧力状態によつて変化
させなければならないから経験が必要であり、も
し急激にバタフライ弁3Aを開くと、原子炉格納
容器1の圧力が急激に下がり、パージ排気フアン
4、プレフイルタ6、高性能粒子フイルタ7等に
損傷を与える恐れがあり好ましくない。
(Problem to be Solved by the Invention) However, the opening degree setting of the butterfly valve 3A requires experience because it must be changed depending on the pressure state inside the reactor containment vessel 1. If 3A is opened, the pressure in the reactor containment vessel 1 will drop rapidly, which may damage the purge exhaust fan 4, prefilter 6, high-performance particle filter 7, etc., which is not preferable.

そこで、本発明の目的は、バタフライ弁を急激
に開動作しても、機器に損傷を与えることがな
く、系統の信頼性を向上させるようにした原子炉
格納容器の漏洩試験用高圧ガスの減圧装置を提供
することにある。
Therefore, an object of the present invention is to reduce the pressure of high-pressure gas for leak testing of reactor containment vessels, which does not damage equipment even if the butterfly valve is suddenly opened and improves system reliability. The goal is to provide equipment.

[発明の構成] (問題点を解決するための手段) 本発明は、原子炉格納容器の漏洩試験用高圧ガ
スを、圧力を調整し、直列に接続されたパージフ
アンおよびフイルタを介して主排気筒から放出し
減圧する原子炉格納容器の漏洩試験用高圧ガスの
減圧装置において、直列に接続されたパージフア
ンおよびフイルタに並列して放圧器を設けたもの
である。
[Structure of the Invention] (Means for Solving the Problems) The present invention adjusts the pressure of high-pressure gas for leak testing of a reactor containment vessel, and passes it through a purge fan and a filter connected in series to the main exhaust stack. In this system, a pressure relief device is installed in parallel with a purge fan and a filter that are connected in series in a pressure reduction device for high pressure gas for leak testing of a reactor containment vessel.

(作用) 通常は漏洩試験用高圧ガスの圧力を調整してか
ら、直列に接続されたパージフアンおよびフイル
タを介して主排気筒から放圧し減圧するが、誤操
作その他の理由で圧力の調整が不十分の場合に
は、漏洩試験用高圧ガスが放圧器を動作して直接
主排気筒から放出し、パージフアンやフイルタに
損傷を与えないようにする。
(Function) Normally, the pressure of the high-pressure gas for leak testing is adjusted and then the pressure is released from the main exhaust stack via a purge fan and filter connected in series to reduce the pressure, but due to incorrect operation or other reasons, the pressure is not adjusted properly. In this case, the high-pressure gas for leak testing operates the pressure relief device and releases it directly from the main exhaust stack to prevent damage to the purge fan or filter.

(実施例) 以下、本発明の一実施例を図面を参照して説明
する。なお、第2図と同一部分には同符号を付
し、重複した説明は省略する。
(Example) Hereinafter, an example of the present invention will be described with reference to the drawings. Note that the same parts as in FIG. 2 are denoted by the same reference numerals, and redundant explanation will be omitted.

第1図は、本発明の一実施例の配管系統図を示
す。同図において、配管2にバタフライ弁3Cと
並行にバタフライ弁3Eを接続し、このバタフラ
イ弁3Eの後にラプチヤデイスク10を接続し、
このラプチヤデイスク10を配管11を介して主
排気筒9に接続する。つまり従来のパージ排気フ
アン4、排気フイルタケーシング5、排気フアン
8をバイパスするラインを新たに追加して設けた
ものである。
FIG. 1 shows a piping system diagram of an embodiment of the present invention. In the same figure, a butterfly valve 3E is connected to the pipe 2 in parallel with the butterfly valve 3C, and a rapture disk 10 is connected after the butterfly valve 3E.
This Lapture disk 10 is connected to the main exhaust pipe 9 via a pipe 11. In other words, a new line is added to bypass the conventional purge exhaust fan 4, exhaust filter casing 5, and exhaust fan 8.

次に、漏洩試験後の減圧について説明する。バ
タフライ弁3Bを閉じバタフライ弁3C,3D,
3Eを全開とし、上記と同様に配管2よりも非常
に細いバタフライ弁3Aを徐々に開くと同時に、
パージ排気フアン4を運転する。これにより、排
気ガスは、排気フイルタケーシング5へ入りプレ
フイルタ6、高性能粒子フイルタ7を通過してダ
スト等を除去した後、常に運転している原子炉建
屋排気フアン8によつて主排気筒9から大気へ放
出される。なお、この場合、ラプチヤデイスク1
0にも排気ガスの圧力はかかるが、この圧力が小
さいのでラプチヤデイスク10は破損しない。
Next, the pressure reduction after the leakage test will be explained. Close the butterfly valve 3B and close the butterfly valves 3C, 3D,
3E is fully opened, and the butterfly valve 3A, which is much thinner than pipe 2, is gradually opened in the same way as above, and at the same time,
Operate purge exhaust fan 4. As a result, the exhaust gas enters the exhaust filter casing 5, passes through the pre-filter 6 and the high-performance particle filter 7, removes dust, etc., and then is transferred to the main exhaust stack 9 by the reactor building exhaust fan 8, which is constantly in operation. released into the atmosphere. In addition, in this case, Laputia disk 1
Although exhaust gas pressure is applied to the 0, the pressure is so small that the Lapture disk 10 will not be damaged.

しかし、何らかの理由でバタフライ弁3Aを急
激に開くと、ラプチヤデイスク10にかかる排気
ガスの圧力も高くなり、これがある圧力以上にな
るとラプチヤデイスク10が破損し、つまりラプ
チヤデイスク10が一種の安全弁の役目をして、
パージ排気フアン4、プレフイルタ6、高性能粒
子フイルタ7、原子炉建屋フアン8をバイパス
し、高圧の排気ガスを直接主排気筒9へ導く。し
たがつて、パージ排気フアン4、プレフイルタ
6、高性能粒子フイルタ7、原子炉建屋排気フア
ン8等の機器を損傷から保護する。
However, if the butterfly valve 3A is suddenly opened for some reason, the pressure of the exhaust gas applied to the Lapcha disk 10 will also increase, and if this pressure exceeds a certain level, the Lapcha disk 10 will be damaged. Acting as a safety valve,
The purge exhaust fan 4, prefilter 6, high performance particle filter 7, and reactor building fan 8 are bypassed, and the high-pressure exhaust gas is guided directly to the main exhaust stack 9. Therefore, equipment such as the purge exhaust fan 4, pre-filter 6, high-performance particle filter 7, and reactor building exhaust fan 8 is protected from damage.

なお、ラプチヤデイスク10の破損後は、バタ
フライ弁3Eを閉とし、新しいラプチヤデイスク
10と取替える。
Note that after the Lapture disk 10 is damaged, the butterfly valve 3E is closed and the Lapture disk 10 is replaced with a new Lapture disk 10.

[発明の効果] 本発明は、以上のように構成されているから、
原子炉格納容器の漏洩試験終了後の高圧ガスの減
圧を、操作手順を誤つても系統に接続されている
機器に損傷を与えることなく行うことができ、系
統の信頼性を向上することができる。
[Effects of the Invention] Since the present invention is configured as described above,
High-pressure gas can be depressurized after a reactor containment vessel leak test is completed without damaging equipment connected to the system even if the operating procedure is incorrect, improving the reliability of the system. .

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は本発明の一実施例を示す配管系統図、
第2図は従来の原子炉格納容器の漏洩試験用ガス
の減圧装置を示す配管系統図である。 1……原子炉格納容器、2,11……配管、3
A,3B,3C,3D,3E……バタフライ弁、
4……パージ排気フアン、5……排気フイルタケ
ーシング、6……プレフイルタ、7……高性能微
粒子フイルタ、8……原子炉建屋排気フアン、9
……主排気筒、10……テプチヤデイスク。
FIG. 1 is a piping system diagram showing an embodiment of the present invention;
FIG. 2 is a piping system diagram showing a conventional pressure reducing device for leak test gas in a reactor containment vessel. 1... Reactor containment vessel, 2, 11... Piping, 3
A, 3B, 3C, 3D, 3E...Butterfly valve,
4... Purge exhaust fan, 5... Exhaust filter casing, 6... Pre-filter, 7... High performance particulate filter, 8... Reactor building exhaust fan, 9
...Main exhaust stack, 10...Teptiya disc.

Claims (1)

【特許請求の範囲】 1 原子炉格納容器の漏洩試験用高圧ガスを、圧
力を調整し、直列に接続されたパージフアンおよ
びフイルタを介して主排気筒から放出し減圧する
原子炉格納容器の漏洩試験用高圧ガスの減圧装置
において、前記直列に接続されたパージフアンお
よびフイルタに並列して放圧器を設けたことを特
徴とする原子炉格納容器の漏洩試験用高圧ガスの
減圧装置。 2 放圧器をラプチヤデイスクとした特許請求の
範囲第1項記載の原子炉格納容器の漏洩試験用高
圧ガスの減圧装置。
[Scope of Claims] 1. Leak test of reactor containment vessel in which high pressure gas for leak test of reactor containment vessel is depressurized by adjusting the pressure and releasing it from the main exhaust stack through a purge fan and filter connected in series. An apparatus for reducing the pressure of high-pressure gas for leak testing of a nuclear reactor containment vessel, characterized in that a pressure relief device is provided in parallel with the purge fan and filter connected in series. 2. A high-pressure gas decompression device for leak testing of a reactor containment vessel as set forth in claim 1, wherein the pressure relief device is a Lapture disc.
JP62169623A 1987-07-09 1987-07-09 Vacuum apparatus of high pressure gas for testing leakage of reactor container Granted JPS6415695A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62169623A JPS6415695A (en) 1987-07-09 1987-07-09 Vacuum apparatus of high pressure gas for testing leakage of reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62169623A JPS6415695A (en) 1987-07-09 1987-07-09 Vacuum apparatus of high pressure gas for testing leakage of reactor container

Publications (2)

Publication Number Publication Date
JPS6415695A JPS6415695A (en) 1989-01-19
JPH0521519B2 true JPH0521519B2 (en) 1993-03-24

Family

ID=15889933

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62169623A Granted JPS6415695A (en) 1987-07-09 1987-07-09 Vacuum apparatus of high pressure gas for testing leakage of reactor container

Country Status (1)

Country Link
JP (1) JPS6415695A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105336381A (en) * 2015-12-07 2016-02-17 上海核工程研究设计院 Air balance device for triple-containment of nuclear power plant

Also Published As

Publication number Publication date
JPS6415695A (en) 1989-01-19

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