JPS63256893A - Leakage detector for pressure vessel of nuclear reactor - Google Patents
Leakage detector for pressure vessel of nuclear reactorInfo
- Publication number
- JPS63256893A JPS63256893A JP62090993A JP9099387A JPS63256893A JP S63256893 A JPS63256893 A JP S63256893A JP 62090993 A JP62090993 A JP 62090993A JP 9099387 A JP9099387 A JP 9099387A JP S63256893 A JPS63256893 A JP S63256893A
- Authority
- JP
- Japan
- Prior art keywords
- leak
- pressure vessel
- reactor pressure
- pipe
- flange
- 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.)
- Pending
Links
- 238000001514 detection method Methods 0.000 claims description 11
- 239000007789 gas Substances 0.000 description 24
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 9
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 4
- 229910001873 dinitrogen Inorganic materials 0.000 description 4
- 238000007689 inspection Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 239000000725 suspension Substances 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Examining Or Testing Airtightness (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
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
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は休止中、たとえば運転開始＋’ｊｌあるいは定
期検査時における原子炉圧力容器のフランジ部の微少漏
洩を検出する原子炉圧力容器の漏洩検出装置に関する。[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) The present invention is an atomic sensor for detecting minute leaks in the flange of a reactor pressure vessel during suspension, for example, during start-up or periodic inspection. This invention relates to a leakage detection device for a reactor pressure vessel.
（従来の技術）
従来運転中の原子炉圧力容器の本体と＃参上蓋との間か
らの漏洩は圧力スイッチによって検出されている。すな
わち第３図および第４図に示すように、原子炉圧力容器
の本体１と上蓋２はフランジ３の接合面で水密に接合さ
れている。フランジ３の接合面には内外２個の０リング
１７．１８が配置され、その間の接合面から１本のリー
クオフ配管４が導出され、原子炉格納容器の壁１１を貫
通したのち圧力スイッチ１０に接続されている。原子炉
が運転中は原子炉圧力容器内部の圧力が高いため、Ｏリ
ング１７． ）８における漏洩があると圧力スイッチ１
０が作動してこれを検知する。(Prior Art) Conventionally, leakage from between the main body of a nuclear reactor pressure vessel and the access cover during operation is detected by a pressure switch. That is, as shown in FIGS. 3 and 4, the main body 1 and the upper cover 2 of the reactor pressure vessel are watertightly joined at the joint surface of the flange 3. Two O-rings 17 and 18, one inside and one outside, are arranged on the joint surface of the flange 3, and one leak-off pipe 4 is led out from the joint surface between them, penetrates the wall 11 of the reactor containment vessel, and then connects to the pressure switch 10. It is connected. When the reactor is operating, the pressure inside the reactor pressure vessel is high, so the O-ring 17. ) If there is a leak at 8, the pressure switch 1
0 is activated and detects this.
これに対し原子炉が休止中の漏洩検査は、原子炉内を満
水にし加圧するので、原子炉圧力容器からの漏水は、リ
ークオフ配管４の中途に設けられた枝管から、ドレンボ
ット１６に集められ、これを検出して判断している。On the other hand, when performing a leakage inspection while the reactor is inactive, the inside of the reactor is filled with water and pressurized, so water leaking from the reactor pressure vessel is collected from a branch pipe installed midway through the leak-off piping 4 into the drain bot 16. , this is detected and determined.
（発明が解決しようとする問題点）
上述した手段では、休止時の検査用の加圧は原子炉運転
中の原子炉圧力容器内の圧力よりもはるかに低くしか加
えられないので、ｉ洩があったとしてもそれが検出され
るまでには非常に長時間を必要とした。またフランジ３
の接合面に、多数のリークオフ配管４を分散配置してこ
れを補うことも可能ではあるが、そのためにはフランジ
３の接合面を、休止中の検査だけのために改造する必要
があった。(Problems to be Solved by the Invention) With the above-mentioned means, the pressurization for inspection during shutdown is only applied at a much lower pressure than the pressure inside the reactor pressure vessel during reactor operation. Even if it existed, it would take a very long time to detect it. Also, flange 3
Although it is possible to compensate for this by distributing a large number of leak-off pipes 4 on the joint surface of the flange 3, it is necessary to modify the joint surface of the flange 3 only for inspection during downtime.
本発明の目的は、原子炉圧力容器のフランジ面に新たな
加工を施すことなく、休止中の原子炉圧力容器の漏洩を
短時間で検出することができる原子炉圧力容器の漏洩検
出装置を提供することにある。An object of the present invention is to provide a leakage detection device for a reactor pressure vessel that can detect leakage in an inactive reactor pressure vessel in a short time without performing any new processing on the flange surface of the reactor pressure vessel. It's about doing.
（問題点を解決するための手段）
本発明においては、原子炉圧力容器の本体と上蓋を接続
するフランジ面に配設された２個のＯリングと、このフ
ランジ面でＯリング間の隙間から原子炉圧力容器の外部
に導出されたリークオフ配管と、このリークオフ配管の
端部に接続された圧力検出手段とを有する原子炉圧力容
器の漏洩検出装置に、上記したリークオフ配管に設けら
れた湿度検出手段と、リークオフ配管から分岐した枝管
に、それぞれ止め弁を介して接続されたガス供給手段お
よびガス吸引手段とを設けた。(Means for Solving the Problem) In the present invention, two O-rings are provided on the flange surface connecting the main body and the upper cover of the reactor pressure vessel, and two O-rings are provided on the flange surface from the gap between the O-rings. A leak detection device for a reactor pressure vessel has a leak-off pipe led out to the outside of the reactor pressure vessel and a pressure detection means connected to an end of the leak-off pipe, and a humidity detection device installed in the leak-off pipe described above is used. A gas supply means and a gas suction means were provided, which were connected to a branch pipe branched from the leak-off pipe through a stop valve, respectively.
（作用）
原子炉を休止し、満水にして加圧した原子炉圧力容器に
対し、止め弁を開いてフランジ面のＯリング間の隙間に
ガス供給手段からガスを供給しておけば、フランジ面に
原子炉圧力容器内の水が漏洩してきた場合、適時止め弁
を開いてガス吸引手段を作動させると、ガス中に拡散し
た漏洩水の水蒸気による温度上昇が湿度検出手段によっ
て検出され、漏洩発生を検知することができる。(Function) If the reactor is shut down and the reactor pressure vessel is filled with water and pressurized, the stop valve is opened and gas is supplied from the gas supply means to the gap between the O-rings on the flange surface. If water leaks from inside the reactor pressure vessel, if the stop valve is opened in a timely manner and the gas suction means is activated, the humidity detection means will detect a temperature rise due to the water vapor of the leaked water that has diffused into the gas, and the leak will occur. can be detected.
（実施例）
以下本発明の一実施例を第１図および第２図を参照して
説明する。(Example) An example of the present invention will be described below with reference to FIGS. 1 and 2.
第１図において、原子炉圧力容器の本体１と上蓋２は、
フランジ３の接合面で水密に接合されている。フランジ
３の接合面には、第２図に拡大して示すように内外２個
の０リング１７．１８が配置され、それらの間の接合面
から１本のリークオフ配管４が導出されている。In FIG. 1, the main body 1 and upper cover 2 of the reactor pressure vessel are
They are watertightly joined at the joint surface of the flange 3. On the joint surface of the flange 3, two inner and outer O-rings 17, 18 are arranged, as shown enlarged in FIG. 2, and one leak-off pipe 4 is led out from the joint surface between them.
リークオフ配管４はリークオフ配管弁１３を介した後、
ｙＫ子炉圧力容器の壁１１を貫通し、計器元弁１５を介
して圧力スイッチ１０に接続されている。またリークオ
フ配管４のリークオフ配管１３より上流から枝管１９が
分岐され、ガス供給元弁１２を介してガス供給ｇ６に接
続されるとともに、枝管１１］からはさらに別個の枝管
２０が分岐され、ガス吸引装置元弁１４を介してガス吸
引装置７に接続されている。After the leak-off piping 4 passes through the leak-off piping valve 13,
It penetrates the wall 11 of the yK child reactor pressure vessel and is connected to the pressure switch 10 via the instrument main valve 15. Further, a branch pipe 19 is branched from upstream of the leak-off pipe 13 of the leak-off pipe 4 and connected to the gas supply g6 via the gas supply source valve 12, and a separate branch pipe 20 is further branched from the branch pipe 11. , is connected to the gas suction device 7 via the gas suction device main valve 14.
ガス供給源６はたとえば窒素ガスボンベとしてもよく、
あるいは原子炉の付属設備である窒素ガス供給系、計装
用空気供給系等であってもよい、さらにリークオフ配管
４の枝管１９の分岐点には湿度センサ５が設けられ、信
号線８によって湿度指示計９に接続されている。The gas supply source 6 may be, for example, a nitrogen gas cylinder,
Alternatively, it may be a nitrogen gas supply system, an instrumentation air supply system, etc. that are attached to the reactor. Furthermore, a humidity sensor 5 is provided at a branch point of a branch pipe 19 of the leak-off pipe 4, and a signal line 8 is connected to a humidity sensor 5. It is connected to indicator 9.
次にこれの作用について説明する。Next, the effect of this will be explained.
原子炉を運転中は、ガス供給元弁１２およびガス吸引装
置元弁１４を閉じ、リークオフ配管弁１３および計器元
弁１５は開いておく。フランジ３を経てＤＫ子炉圧力容
器から漏洩があると、リークオフ配管４を通じて原子炉
圧力容器内の圧力が圧力スイッチ１０に加わり、漏洩が
検出される。While the reactor is operating, the gas supply source valve 12 and the gas suction device source valve 14 are closed, and the leak-off pipe valve 13 and instrument source valve 15 are kept open. If there is a leak from the DK child reactor pressure vessel via the flange 3, the pressure inside the reactor pressure vessel is applied to the pressure switch 10 through the leak-off pipe 4, and the leak is detected.
原子炉を休止して原子炉圧力容器の耐圧漏洩試験を行な
う時には、リークオフ配管弁１３および計器元弁１５を
閉じ、ガス供給元弁１２を開いて乾燥した窒素ガス（ま
たは空気）を、リークオフ配管４を通じてフランジ３の
接合面の隙間に満たす、このときの湿度指示計９の読み
が基準値として記録される０次いで原子炉圧力容器は満
水加圧され漏洩検査が開始さ、れる。When shutting down the reactor and performing a pressure leakage test on the reactor pressure vessel, the leak-off piping valve 13 and instrument main valve 15 are closed, the gas supply source valve 12 is opened, and dry nitrogen gas (or air) is supplied to the leak-off piping. The reading of the humidity indicator 9 at this time is recorded as a reference value.Then, the reactor pressure vessel is filled with water and pressurized, and a leakage test is started.
適時ガス供給元弁１２を閉じ、ガス吸引装置元弁１４を
開いてガス吸引装置７を運転する。このときもしフラン
ジ３の接合面に漏洩が生じていれば、漏洩水はリークオ
フ配管４を満たす窒素ガス中に水蒸気となって拡散し、
ガス中の湿度が上昇する。The gas supply source valve 12 is closed at an appropriate time, the gas suction device source valve 14 is opened, and the gas suction device 7 is operated. At this time, if a leak occurs at the joint surface of the flange 3, the leaked water becomes water vapor and diffuses into the nitrogen gas filling the leak-off pipe 4.
Humidity in the gas increases.
ブ
この湿度上昇は湿度セン−ＳＳによって検知され、漏洩
の発生が認知される。ガス吸引装置７によってガスを吸
引しているので、フランジ３の接合面の空隙のどこで漏
洩が発生しても、早期に湿度−ヒ昇が検知されて漏洩を
発見することができる。This increase in humidity is detected by the humidity sensor SS, and the occurrence of a leak is recognized. Since the gas is sucked by the gas suction device 7, even if a leak occurs anywhere in the gap between the joint surfaces of the flange 3, an increase in humidity can be detected at an early stage and the leak can be discovered.
本発明によれば、原子炉圧力容器自体には何等変更を加
えることなく、休止中の原子炉圧力容器の漏洩試験を短
時間で行なうことができるという効果がある。According to the present invention, there is an effect that a leakage test of a nuclear reactor pressure vessel that is inactive can be conducted in a short time without making any changes to the reactor pressure vessel itself.
第１図は本発明の一実施例を示す系統図、第２図は第１
図の要部を拡大して示す断面図、第３図は従来の原子炉
圧力容器の漏洩検出装置を示す系統図、第４図は第３図
のＡ−Ａ線矢視断面図である。
１・・・本体 ２・・・」；蓋３・・・フ
ランジ ４・・・リークオフ配管５・・・湿度
センサ ６・・・ガス供給源７・・・ガス吸引袋
Ｆｔ １０・・・圧力スイッチ１２・・・ガス供
給元弁 １４・・・ガス吸引装置元弁１７、１８・
・・０リング １９．２０・・・枝管代理人 弁理
士 則 近 憲 佑
同 第子丸 健
第１図
第２図
第４図Fig. 1 is a system diagram showing one embodiment of the present invention, and Fig. 2 is a system diagram showing an embodiment of the present invention.
FIG. 3 is a system diagram showing a conventional leak detection device for a reactor pressure vessel, and FIG. 4 is a cross-sectional view taken along the line A--A in FIG. 3. 1...Body 2..."; Lid 3...Flange 4...Leak-off piping 5...Humidity sensor 6...Gas supply source 7...Gas suction bag Ft 10...Pressure switch 12... Gas supply source valve 14... Gas suction device source valve 17, 18.
...0 ring 19.20...Branch agent Patent attorney Nori Chika Ken Yudo Daishimaru Ken Figure 1 Figure 2 Figure 4
Claims (1)
に配設された２個のＯリングと、前記フランジ面で前記
２個のＯリング間の細隙から前記原子炉圧力容器の外部
に導出されたリークオフ配管と、このリークオフ配管の
端部に接続された圧力検出手段とを有する原子炉圧力容
器の漏洩検出装置において、前記リークオフ配管に設け
られた湿度検出手段と、前記リークオフ配管から分岐し
た枝管にそれぞれ止め弁を介して接続されたガス供給手
段およびガス吸引手段を有することを特徴とする原子炉
圧力容器の漏洩検出装置。1. Two O-rings are installed on the flange surface connecting the main body and the top cover of the reactor pressure vessel, and the flange is connected to the outside of the reactor pressure vessel through the narrow gap between the two O-rings on the flange surface. A leak detection device for a reactor pressure vessel having a lead-out leak-off pipe and a pressure detection means connected to an end of the leak-off pipe, the humidity detection means provided in the leak-off pipe and a branch from the leak-off pipe. A leak detection device for a nuclear reactor pressure vessel, comprising a gas supply means and a gas suction means, each connected to a branch pipe via a stop valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62090993A JPS63256893A (en) | 1987-04-15 | 1987-04-15 | Leakage detector for pressure vessel of nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62090993A JPS63256893A (en) | 1987-04-15 | 1987-04-15 | Leakage detector for pressure vessel of nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63256893A true JPS63256893A (en) | 1988-10-24 |
Family
ID=14014036
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62090993A Pending JPS63256893A (en) | 1987-04-15 | 1987-04-15 | Leakage detector for pressure vessel of nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63256893A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0902439A3 (en) * | 1997-09-11 | 1999-06-23 | Siemens Aktiengesellschaft | Leakage monitoring device and method of operating such a device |
| JP2010281359A (en) * | 2009-06-03 | 2010-12-16 | Bridgestone Corp | Pipe joint |
| KR20180105672A (en) * | 2016-03-29 | 2018-09-28 | 비고 가스 퓨리피케이션 테크놀로지스 인코포레이티드 | On-line hermetically sealed inspection apparatus, multi-section type closed chamber processing apparatus and method |
-
1987
- 1987-04-15 JP JP62090993A patent/JPS63256893A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0902439A3 (en) * | 1997-09-11 | 1999-06-23 | Siemens Aktiengesellschaft | Leakage monitoring device and method of operating such a device |
| JP2010281359A (en) * | 2009-06-03 | 2010-12-16 | Bridgestone Corp | Pipe joint |
| KR20180105672A (en) * | 2016-03-29 | 2018-09-28 | 비고 가스 퓨리피케이션 테크놀로지스 인코포레이티드 | On-line hermetically sealed inspection apparatus, multi-section type closed chamber processing apparatus and method |
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