JPS6367679B2 - - Google Patents

Info

Publication number
JPS6367679B2
JPS6367679B2 JP56032532A JP3253281A JPS6367679B2 JP S6367679 B2 JPS6367679 B2 JP S6367679B2 JP 56032532 A JP56032532 A JP 56032532A JP 3253281 A JP3253281 A JP 3253281A JP S6367679 B2 JPS6367679 B2 JP S6367679B2
Authority
JP
Japan
Prior art keywords
main steam
isolation valve
steam isolation
reactor
leakage
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
Application number
JP56032532A
Other languages
Japanese (ja)
Other versions
JPS57147089A (en
Inventor
Takashi Tokunaga
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 Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
Toshiba Corp
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 Toshiba Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP56032532A priority Critical patent/JPS57147089A/en
Publication of JPS57147089A publication Critical patent/JPS57147089A/en
Publication of JPS6367679B2 publication Critical patent/JPS6367679B2/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

  • Examining Or Testing Airtightness (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は沸騰水形原子炉の原子炉圧力容器に設
けた複数の主蒸気管の主蒸気隔離弁閉止の際の漏
洩を、所望の弁のみについて検知できる漏洩試験
装置およびその方法に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention provides a leak testing device that can detect leakage of only desired valves when the main steam isolation valves of a plurality of main steam pipes installed in the reactor pressure vessel of a boiling water reactor are closed. and its method.

主蒸気隔離弁は、環境への放射性物質放出防止
という機能の重要性から、定期点検時におけるプ
ラント停止直後とプラント起動直前に主蒸気ドレ
ンラインを利用して漏洩試験を実施している。こ
の主蒸気隔離弁の漏洩試験は、原子炉格納容器内
及び原子炉格納容器外のどちらか4個の弁を同時
に実施している。原子炉格納容器内にある内側主
蒸気隔離弁の漏洩試験は、その内側および外側の
全主蒸気隔離弁を閉じ、内側主蒸気隔離弁に接続
した内側主蒸気ドレン配管を利用して、内側主蒸
気隔離弁より原子炉圧力容器側の主蒸気管を試験
圧力まで空気加圧し、内側主蒸気隔離弁よりター
ビン側主蒸気管に設けた圧力測定装置にて漏洩を
検出している。又、原子炉格納容器外にある外側
主蒸気隔離弁の漏洩試験は、内外両側の全主蒸気
隔離弁を閉じ、内側主蒸気ドレンラインを利用し
て内側主蒸気隔離弁より原子炉圧力容器側の主蒸
気管を空気加圧及び水張り(内側主蒸気隔離弁が
完全に水没するまで)したのち、内側と外側の主
蒸気隔離弁の間の弁間主蒸気管を、外側主蒸気隔
離弁に接続した外側主蒸気ドレン排管から試験圧
力まで空気加圧し、圧力降下法により圧力測定装
置にて漏洩検出を実施している。
Due to the importance of the main steam isolation valve's function of preventing the release of radioactive materials into the environment, leakage tests are conducted using the main steam drain line immediately after the plant is shut down during periodic inspections and immediately before the plant is started. This main steam isolation valve leakage test is conducted simultaneously on four valves, either inside the reactor containment vessel or outside the reactor containment vessel. A leak test for the inner main steam isolation valve in the reactor containment vessel is performed by closing all the inner and outer main steam isolation valves, and using the inner main steam drain piping connected to the inner main steam isolation valve to test the inner main steam isolation valve. Air is pressurized to the main steam pipe on the reactor pressure vessel side from the steam isolation valve to the test pressure, and leakage is detected using a pressure measuring device installed in the main steam pipe on the turbine side from the inner main steam isolation valve. In addition, for leakage tests of the outer main steam isolation valve located outside the reactor containment vessel, all main steam isolation valves on both the inside and outside sides are closed, and the inner main steam drain line is used to connect the inner main steam isolation valve to the reactor pressure vessel side. After pressurizing the main steam pipe with air and filling it with water (until the inner main steam isolation valve is completely submerged), connect the intervalve main steam pipe between the inner and outer main steam isolation valves to the outer main steam isolation valve. Air is pressurized to the test pressure from the connected outer main steam drain pipe, and leakage is detected using a pressure measurement device using the pressure drop method.

ところで、全部の主蒸気隔離弁を対象とする定
期点検時におけるプラント停止直後と、プラント
起動直前とに行なう主蒸気隔離弁の漏洩試験で
は、内側及び外側のどちらか4個(片側全個数)
の主蒸気隔離弁を同時に実施することにより、試
験時間を短縮できるが、主蒸気隔離弁のラツピン
グを行なつた後、その主蒸気隔離弁だけの仮の漏
洩試験を実施したい場合でも、他の主蒸気隔離弁
と一しよに試験を実施している。このように試験
を行なう必要のない他の主蒸気隔離弁までも一し
よに試験をすると、空気加圧又は空気加圧及び水
張りを行なう時間が長くなり、漏洩試験の工程の
遅れの大きな原因となる。
By the way, in the main steam isolation valve leakage test conducted immediately after the plant is stopped and immediately before the plant is started during periodic inspections that target all main steam isolation valves, either four inside or outside (total number on each side)
Testing time can be shortened by performing multiple main steam isolation valve tests at the same time. Tests are being conducted together with the main steam isolation valve. If other main steam isolation valves that do not need to be tested are also tested in this way, the time required for air pressurization or air pressurization and water filling becomes longer, which is a major cause of delays in the leak test process. becomes.

本発明の目的は、複数個ある主蒸気隔離弁のう
ち、任意のもののみについて漏洩を検知できる原
子炉の主蒸気隔離弁漏洩試験装置およびその方法
を提供することにある。
An object of the present invention is to provide a main steam isolation valve leak testing device for a nuclear reactor and a method therefor, which can detect leakage from only any one of a plurality of main steam isolation valves.

以下、本発明の一実施例について、図面を参照
して説明する。図は主蒸気隔離弁漏洩試験設備配
管系統図である。
An embodiment of the present invention will be described below with reference to the drawings. The figure is a piping system diagram of the main steam isolation valve leak test equipment.

原子炉圧力容器1から出る主蒸気管2,3,
4,5の途中には原子炉格納容器壁29を貫通す
る内外部に内側主蒸気隔離弁6,7,8,9と外
側主蒸気隔離弁10,11,12,13が取付け
られている。内側主蒸気隔離弁6〜9から、それ
ぞれ内側主蒸気ドレン配管14,15,16,1
7を設け、外側主蒸気隔離弁から、それぞれ外側
主蒸気ドレン配管25,26,27,28を設け
る。内側主蒸気ドレン配管14〜17にはそれぞ
れ止め弁18,19,20,21を設け、これを
統合主蒸気ドレン配管22に統合する。外側主蒸
気ドレン配管25〜28には、それぞれ圧力計の
ような圧力測定装置30,31,32,33を設
ける。統合主蒸気ドレン配管22が原子炉格納容
器壁29を貫通する内外にはドレン用隔離弁2
3,24を設ける。
Main steam pipes 2, 3, exiting from the reactor pressure vessel 1
Inner main steam isolation valves 6, 7, 8, 9 and outer main steam isolation valves 10, 11, 12, 13 are attached to the inside and outside of the reactor containment vessel wall 29 in the middle of the reactor containment vessel walls 29, respectively. From the inner main steam isolation valves 6 to 9, inner main steam drain pipes 14, 15, 16, 1, respectively.
7 is provided, and outer main steam drain pipes 25, 26, 27, and 28 are provided from the outer main steam isolation valve, respectively. Stop valves 18, 19, 20, and 21 are provided on the inner main steam drain pipes 14 to 17, respectively, and these are integrated into an integrated main steam drain pipe 22. The outer main steam drain pipes 25 to 28 are provided with pressure measuring devices 30, 31, 32, and 33, respectively, such as pressure gauges. Drain isolation valves 2 are installed inside and outside where the integrated main steam drain pipe 22 penetrates the reactor containment vessel wall 29.
3 and 24 are provided.

この装置を用いて、第1の内側主蒸気隔離弁6
について漏洩試験を実施する場合は、主蒸気管2
に設置されている内外両側の主蒸気隔離弁6,1
0及び、他系統の内側主蒸気隔離弁7〜9に設け
られた内側主蒸気ドレン配管の止め弁19〜21
を閉じ、原子炉圧力容器1の容器蓋1aを除き、
主蒸気管2の開口部に蓋34を被せてこれを閉じ
る。その後統合主蒸気ドレン配管22および内側
主蒸気ドレン配管14を利用して第1の内側主蒸
気隔離弁6より原子炉圧力容器1側主蒸気管2を
試験圧力まで空気加圧し、ドレン用隔離弁23,
24を閉じて保持する。
Using this device, the first inner main steam isolation valve 6
When performing a leak test on main steam pipe 2
The main steam isolation valves 6, 1 on both the inside and outside sides are installed in
Stop valves 19 to 21 of the inner main steam drain piping provided in the inner main steam isolation valves 7 to 9 of 0 and other systems
Close the reactor pressure vessel 1, remove the vessel lid 1a,
A lid 34 is placed over the opening of the main steam pipe 2 and closed. Thereafter, the main steam pipe 2 on the reactor pressure vessel 1 side is pressurized with air to the test pressure from the first inner main steam isolation valve 6 using the integrated main steam drain pipe 22 and the inner main steam drain pipe 14, and the drain isolation valve is 23,
Close and hold 24.

第1の主蒸気隔離弁6から漏洩があつた場合
は、第1の外側主蒸気ドレン配管に設けた圧力測
定装置30にて検出できる。尚この場合は圧力測
定装置30は圧力計でなくU字管でも検出でき
る。
If there is a leak from the first main steam isolation valve 6, it can be detected by a pressure measuring device 30 provided on the first outer main steam drain pipe. In this case, the pressure measuring device 30 may be a U-shaped tube instead of a pressure gauge.

次に第1の外側主蒸気隔離弁10の漏洩試験を
する場合は、前記第1の内側主蒸気隔離弁6の試
験のように空気加圧したならば、その内側主蒸気
隔離弁6が完全に水没する迄水張りする。その
後、内側と外側の主蒸気隔離弁6,10の間の第
1の弁間主蒸気管2aを第1の外側主蒸気ドレン
配管25を利用して試験圧力まで空気加圧し、圧
力降下法により第1の圧力測定装置30にて漏洩
の有無を検出する。この場合は圧力測定装置30
としては圧力計が適し、U字管は不適当である。
Next, when performing a leakage test on the first outer main steam isolation valve 10, if the air is pressurized as in the test of the first inner main steam isolation valve 6, the inner main steam isolation valve 6 is completely Fill with water until it is completely submerged. Thereafter, the first inter-valve main steam pipe 2a between the inner and outer main steam isolation valves 6, 10 is pressurized with air to the test pressure using the first outer main steam drain pipe 25, and the pressure drop method is used. The first pressure measuring device 30 detects the presence or absence of leakage. In this case, the pressure measuring device 30
A pressure gauge is suitable; a U-shaped tube is not suitable.

次に作用について説明する。 Next, the effect will be explained.

この実施例においては止め弁18〜21を用い
て所定の内側主蒸気隔離弁例えば6の原子炉圧力
容器1側のみを選択して空気加圧又は空気加圧及
び水張りするようにしたことにより、その空気加
圧又は空気加圧及び水張りに要する時間が短縮さ
れ、漏洩試験を短時間に行なうことができる。主
蒸気隔離弁を2個又は3個或いは全個数同時に漏
洩試験するときは、それに応じた止め弁18〜2
1を適宜選択して開放するようにすればよいこと
は勿論である。
In this embodiment, the stop valves 18 to 21 are used to select only the reactor pressure vessel 1 side of a predetermined inner main steam isolation valve, for example 6, to pressurize air or to pressurize air and fill with water. The time required for air pressurization or air pressurization and water filling can be shortened, and leakage tests can be conducted in a short time. When performing a leak test on two, three, or all main steam isolation valves at the same time, the appropriate stop valves 18 to 2
Of course, it is sufficient to select 1 as appropriate and open it.

尚、本発明は上記し、かつ図面に示した実施例
のみに限定されるものではなく、その要旨を変更
しない範囲で、種々変形して実施できることは勿
論である。
It should be noted that the present invention is not limited to the embodiments described above and shown in the drawings, but can of course be implemented with various modifications without changing the gist thereof.

以上説明したように、本発明によれば、複数の
内側主蒸気隔離弁にそれぞれ設けた内側主蒸気ド
レン配管の止め弁を適宜選択して、所定の内側主
蒸気隔離弁の原子炉圧力容器側のみを空気加圧又
は空気加圧及び水張りするようにしたことによ
り、所定の主蒸気隔離弁のみを短時間に漏洩試験
を行なうことができる効果がある。
As explained above, according to the present invention, the stop valves of the inner main steam drain piping provided in each of the plurality of inner main steam isolation valves are appropriately selected, and By pressurizing only the main steam isolation valves with air or pressurizing them with air and filling them with water, it is possible to conduct a leakage test on only the predetermined main steam isolation valves in a short period of time.

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

添付図面は本発明の原子炉の主蒸気隔離弁漏洩
試験方法の一実施例を行なう装置の配管系統図で
ある。 1…原子炉圧力容器、2〜5…主蒸気管、2a
〜5a…弁間主蒸気管、6〜9…内側主蒸気隔離
弁、10〜13…外側主蒸気隔離弁、14〜17
…内側主蒸気ドレン配管、18〜21…止め弁、
22…統合主蒸気ドレン配管、25〜28…外側
主蒸気ドレン配管、29…原子炉格納容器壁、3
0〜33…圧力測定装置、34〜37…蓋。
The accompanying drawing is a piping system diagram of an apparatus for carrying out an embodiment of the main steam isolation valve leakage testing method for a nuclear reactor according to the present invention. 1...Reactor pressure vessel, 2-5...Main steam pipe, 2a
~5a... Inter-valve main steam pipe, 6-9... Inner main steam isolation valve, 10-13... Outer main steam isolation valve, 14-17
...Inner main steam drain piping, 18-21...stop valve,
22... Integrated main steam drain piping, 25-28... Outer main steam drain piping, 29... Reactor containment vessel wall, 3
0-33...Pressure measuring device, 34-37...Lid.

Claims (1)

【特許請求の範囲】 1 沸騰水形原子炉の原子炉圧力容器に複数の主
蒸気管を結合し、これで原子炉格納容器壁を貫通
させ、その貫通部の内外に主蒸気隔離弁を設けて
タービンに蒸気を供給する装置の前記主蒸気隔離
弁の閉止の際の漏洩を検知する試験装置におい
て、各内側主蒸気隔離弁にはそれぞれ内側主蒸気
ドレン排管を設け、これをそれぞれ止め弁を介し
て統合主蒸気ドレン配管に接続し、各外側主蒸気
隔離弁にはそれぞれ圧力測定装置を有する外側主
蒸気ドレン配管を設け、内側主蒸気隔離弁に連通
する主蒸気管の原子炉圧力容器内開口部に漏洩試
験の際に被せる蓋を備えたことを特徴とする原子
炉の主蒸気隔離弁漏洩試験装置。 2 沸騰水形原子炉の原子炉圧力容器に複数の主
蒸気管を結合し、これで原子炉格納容器壁を貫通
させ、その貫通部の内外に主蒸気隔離弁を設けて
タービンに蒸気を供給する装置の前記主蒸気隔離
弁の閉止の際の漏洩を検知する試験方法におい
て、各内側主蒸気隔離弁にはそれぞれ内側主蒸気
ドレン排管を設け、これをそれぞれ止め弁を介し
て統合主蒸気ドレン配管に接続し、各外側主蒸気
隔離弁にはそれぞれ圧力測定装置を有する外側主
蒸気ドレン配管を設け、所定の内側主蒸気隔離弁
に連通する主蒸気管の原子炉圧力容器内開口部に
蓋をし、前記止め弁を選択して所定の主蒸気ドレ
ン排管から前記所定の内側主蒸気隔離弁に空気加
圧又は空気加圧及び水張りして、前記圧力測定装
置により前記所定の内側主蒸気隔離弁又はそれに
連通する外側主蒸気隔離弁の漏洩を検知すること
を特徴とする原子炉の主蒸気隔離弁漏洩試験方
法。 3 内側主蒸気隔離弁の漏洩試験をするときは、
その内側主蒸気隔離弁とそれに連なる外側主蒸気
隔離弁とを閉じ、内側主蒸気隔離弁より原子炉圧
力容器側の主蒸気管を空気加圧して漏洩を検知す
ることを特徴とする特許請求の範囲第2項記載の
原子炉の主蒸気隔離弁漏洩試験方法。 4 外側主蒸気隔離弁の漏洩試験をするときは、
その外側主蒸気隔離弁とそれに連なる内側主蒸気
隔離弁とを閉じ、内側主蒸気隔離弁より原子炉圧
力容器側の主蒸気管を空気加圧及び水張りした
後、外側主蒸気ドレン配管により弁間の主蒸気管
を空気加圧し、漏洩を検知することを特徴とする
特許請求の範囲第2項記載の原子炉の主蒸気隔離
弁漏洩試験方法。
[Claims] 1. A plurality of main steam pipes are connected to the reactor pressure vessel of a boiling water reactor, penetrate the reactor containment vessel wall, and provide main steam isolation valves inside and outside of the penetration part. In a test device for detecting leakage when the main steam isolation valve of a device that supplies steam to a turbine is closed, each inner main steam isolation valve is provided with an inner main steam drain exhaust pipe, which is connected to a stop valve. each outer main steam isolation valve is provided with an outer main steam drain pipe having a pressure measuring device, and the reactor pressure vessel of the main steam pipe communicating with the inner main steam isolation valve is connected to the integrated main steam drain piping through the A main steam isolation valve leakage testing device for a nuclear reactor, characterized in that an inner opening is provided with a lid that is covered during a leakage test. 2 A plurality of main steam pipes are connected to the reactor pressure vessel of a boiling water reactor, and these pipes penetrate the reactor containment vessel wall, and main steam isolation valves are installed inside and outside the penetration part to supply steam to the turbine. In the test method for detecting leakage when the main steam isolation valve of a device is closed, each inner main steam isolation valve is provided with an inner main steam drain drain pipe, which is connected to the integrated main steam through a stop valve. Each outer main steam isolation valve is connected to a drain pipe, and each outer main steam isolation valve is provided with an outer main steam drain pipe having a pressure measuring device, and the opening in the reactor pressure vessel of the main steam pipe communicating with a predetermined inner main steam isolation valve is cover, select the stop valve, pressurize air or pressurize air and fill with water from a predetermined main steam drain pipe to the predetermined inner main steam isolation valve, and use the pressure measuring device to A method for testing a main steam isolation valve for a nuclear reactor, characterized by detecting leakage in a steam isolation valve or an outer main steam isolation valve communicating therewith. 3. When performing a leakage test on the inner main steam isolation valve,
The inner main steam isolation valve and the outer main steam isolation valve connected thereto are closed, and the main steam pipe on the reactor pressure vessel side is pressurized with air from the inner main steam isolation valve to detect leakage. A main steam isolation valve leak test method for a nuclear reactor as described in Scope 2. 4 When performing a leakage test on the outer main steam isolation valve,
The outer main steam isolation valve and the inner main steam isolation valve connected to it are closed, and after the main steam pipe on the reactor pressure vessel side is pressurized with air and filled with water from the inner main steam isolation valve, the outer main steam drain pipe is connected between the valves. 3. A method for testing leakage of a main steam isolation valve in a nuclear reactor according to claim 2, wherein leakage is detected by pressurizing the main steam pipe of a nuclear reactor.
JP56032532A 1981-03-09 1981-03-09 Method and device for testing leakage of main steam isolation valve of nuclear reactor Granted JPS57147089A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56032532A JPS57147089A (en) 1981-03-09 1981-03-09 Method and device for testing leakage of main steam isolation valve of nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56032532A JPS57147089A (en) 1981-03-09 1981-03-09 Method and device for testing leakage of main steam isolation valve of nuclear reactor

Publications (2)

Publication Number Publication Date
JPS57147089A JPS57147089A (en) 1982-09-10
JPS6367679B2 true JPS6367679B2 (en) 1988-12-27

Family

ID=12361545

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56032532A Granted JPS57147089A (en) 1981-03-09 1981-03-09 Method and device for testing leakage of main steam isolation valve of nuclear reactor

Country Status (1)

Country Link
JP (1) JPS57147089A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH057514Y2 (en) * 1990-06-20 1993-02-25

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60164300A (en) * 1984-02-07 1985-08-27 株式会社東芝 Test apparatus for leakage from main steam separating valve

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH057514Y2 (en) * 1990-06-20 1993-02-25

Also Published As

Publication number Publication date
JPS57147089A (en) 1982-09-10

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