JPS62177427A - Leak detecting method for double heat conduction tube vapor generator - Google Patents
Leak detecting method for double heat conduction tube vapor generatorInfo
- Publication number
- JPS62177427A JPS62177427A JP61019457A JP1945786A JPS62177427A JP S62177427 A JPS62177427 A JP S62177427A JP 61019457 A JP61019457 A JP 61019457A JP 1945786 A JP1945786 A JP 1945786A JP S62177427 A JPS62177427 A JP S62177427A
- Authority
- JP
- Japan
- Prior art keywords
- pressure
- tube
- internal
- helium
- leaks
- 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
- 238000000034 method Methods 0.000 title claims description 3
- 239000007788 liquid Substances 0.000 claims abstract description 17
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims abstract description 15
- 229910052708 sodium Inorganic materials 0.000 claims abstract description 15
- 239000011734 sodium Substances 0.000 claims abstract description 15
- 239000001307 helium Substances 0.000 claims abstract description 11
- 229910052734 helium Inorganic materials 0.000 claims abstract description 11
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims abstract description 11
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 8
- 238000001514 detection method Methods 0.000 description 5
- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical compound C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 description 4
- 230000007423 decrease Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000003345 natural gas Substances 0.000 description 2
- 238000004891 communication Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000006193 liquid solution Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000008439 repair process Effects 0.000 description 1
- 230000004043 responsiveness Effects 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
Description
【発明の詳細な説明】
[産業上の利用分野]
本発明は、高速増殖炉原子力設備に於ける2重伝熱管蒸
気発生器のリーク検出方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to a leak detection method for a double heat exchanger tube steam generator in a fast breeder reactor nuclear power facility.
F従来の技術]
通常高速増殖炉に於いては炉心で発生した核分裂による
熱を1次熱媒体である液体ナトリウムによって取出し、
中間熱交換器に於いて2次液体ナトリウムと熱交換し、
更に2次液体ナトリウムを蒸気発生器に導びき該蒸気発
生器で作動媒体である水と熱交換させて蒸気を発生させ
ている。或はプラントの合理化のために中間熱交換器を
省略し1次液体ナトリウムを直接蒸気発生器に導びぎ蒸
気を発生させるシステムも発案されている。F. Conventional technology] Normally, in a fast breeder reactor, heat from nuclear fission generated in the reactor core is extracted using liquid sodium, which is the primary heat carrier.
Exchange heat with secondary liquid sodium in an intermediate heat exchanger,
Further, the secondary liquid sodium is led to a steam generator, where it exchanges heat with water, which is a working medium, to generate steam. Alternatively, in order to rationalize the plant, a system has been proposed in which the intermediate heat exchanger is omitted and primary liquid sodium is directly guided to a steam generator to generate steam.
斯かる然気発生器に於いて、液体す1〜リウム ゛と水
とを伝熱管を介して熱交換させる為、伝熱管にクラック
が入り水が液体ナトリウムにリークすると液体すトリウ
ムと水とが激しく反応して大事故をjOり。特に中間熱
交換器を省略した設備に於いては液体ナトリウムが放則
能を帯びている為事故の影響が大きく、更に蒸気発生器
が原子炉容器に近接している為事故の影響が原子炉容器
に迄及び薔く極めて危険である。In such a natural gas generator, heat is exchanged between liquid sodium and water via heat transfer tubes, so if a crack occurs in the heat transfer tube and water leaks into liquid sodium, liquid sodium and water will be exchanged. He reacted violently and caused a major accident. In particular, in equipment that does not have an intermediate heat exchanger, the influence of an accident is large because the liquid sodium has a radioactive capacity, and the steam generator is close to the reactor vessel, so the influence of an accident is It is extremely dangerous if it spreads all the way to the container.
而して、蒸気発生器の信頼性、安全性を向上させる為、
伝熱管を2重伝熱管とし、更に伝熱管の内管、外管のい
ずれか1方にクラックが入りリークした場合、内管、外
管の間隙にリークした水等を検出することにより内管、
外管のクラックの発生を検知し大事故に到る前に補修等
を行おうとするものが発案されている。Therefore, in order to improve the reliability and safety of the steam generator,
If the heat exchanger tube is a double heat exchanger tube and either the inner tube or the outer tube of the heat exchanger tube has a crack and leaks, the inner tube can be removed by detecting water leaking into the gap between the inner tube and the outer tube. ,
A system has been proposed that detects the occurrence of cracks in the outer pipe and repairs them before a major accident occurs.
第2図は2重伝熱管の蒸気発生器の概略を示すものであ
る。圧力容器1の上部、下部にそれぞれ外管管板2,3
、内管管板4,5を設け、これら管板間に2重伝熱管6
を掛渡して設ける。外管7の端部は第3図に示す如く外
管管板2.3に溶接し、内管8の端部は内管管板4,5
に溶接する。尚、図では伝熱管は省略して1本のみ示し
ておる。ここで内管8と外管7間の僅かな間隙は外管管
板と内管管板によって画成される空間9.10と連通さ
せである。FIG. 2 schematically shows a steam generator with double heat exchanger tubes. Outer tube plates 2 and 3 are installed at the upper and lower parts of the pressure vessel 1, respectively.
, inner tube tube sheets 4 and 5 are provided, and a double heat exchanger tube 6 is installed between these tube sheets.
It is set up by hanging it. The end of the outer tube 7 is welded to the outer tube sheet 2.3 as shown in FIG. 3, and the end of the inner tube 8 is welded to the inner tube sheet 4, 5.
Weld to. In addition, the heat exchanger tube is omitted in the figure and only one is shown. Here, the small gap between the inner tube 8 and the outer tube 7 is in communication with the space 9.10 defined by the outer tube plate and the inner tube plate.
現在発案されているものの1として、前記空間9,10
を介して約20K(]/Cm2程の圧力のヘリウムガス
(I−1c)を内管8と外管7間の間隙に流通させ、分
析器11によりHe中の水分(H2O>の検出をし、又
、分析器16により、液体ナトリウム中のHeを検出し
ようとするものがある。One of the things currently being proposed is the spaces 9 and 10.
Helium gas (I-1c) at a pressure of about 20 K(]/Cm2 is passed through the gap between the inner tube 8 and the outer tube 7 through the analyzer 11 to detect moisture (H2O>) in He. There is also an attempt to detect He in liquid sodium using the analyzer 16.
ここで、内管内を流れる蒸気圧力は約130KMcm2
であり、外管外を流れる液体すI・リウムの圧力は約5
にg/cm2である。Here, the pressure of steam flowing inside the inner pipe is approximately 130KMcm2.
, and the pressure of the liquid I/Rium flowing outside the outer tube is approximately 5
g/cm2.
し発明がM’決しようとする問題点コ
然し、上記方法ではHeを循環させる為の循環系12を
必要とし且He中のH2Oを検出する分析器11又液体
ナトリウム中のHeを検出する分析器16を必要とし、
リーク検出系の装備が面倒である。However, the above method requires a circulation system 12 for circulating He, and an analyzer 11 for detecting H2O in He or an analysis device for detecting He in liquid sodium. requires 16 vessels,
The leak detection system is troublesome to equip.
本発明は、上記実情に鑑み簡単な構成にして而も内管、
外管のいずれもが損傷しても、そのff1mを検知し得
るリーク検出方法を提供しようとするものである。In view of the above-mentioned circumstances, the present invention has a simple structure and an inner tube,
The present invention aims to provide a leak detection method that can detect ff1m even if any of the outer tubes is damaged.
[問題点を解決するための手段」
本発明は、伝熱管を2重管とし伝熱管外部に液体ナトリ
ウムを流し、伝熱管内部に水を流して蒸気を発生させる
2重管蒸気発生器に於いて伝熱管の内管、外管の間に内
管内圧J:り高圧のヘリウムを封入し、該ヘリウムの圧
力変化を検知してリーク検出を行うことを特徴とするも
のである。[Means for Solving the Problems] The present invention provides a double-tube steam generator in which the heat exchanger tube is a double tube, liquid sodium flows outside the heat exchanger tube, and water flows inside the heat exchanger tube to generate steam. This is characterized in that helium at a high pressure within the inner tube is sealed between the inner tube and the outer tube of the heat transfer tube, and leakage detection is performed by detecting the pressure change of the helium.
[作 用]
液体ナトリiクムは内管内部圧力(水圧力)よりも低く
、封入したヘリウムは伝熱管の内外圧力よりも高い。従
って、内管、外管のいずれに11傷があってもリークが
発生しヘリウム圧力が低下し、その圧力検知によってリ
ークを検出することができる。[Function] The liquid sodium i-cum is lower than the internal pressure of the inner tube (water pressure), and the sealed helium is higher than the internal and external pressure of the heat transfer tube. Therefore, even if there are 11 scratches on either the inner tube or the outer tube, a leak will occur and the helium pressure will drop, and the leak can be detected by detecting the pressure.
[実 施 例] 以下図面を参照しつつ本発明の詳細な説明する。[Example] The present invention will be described in detail below with reference to the drawings.
尚、第1図中第2図に於いて示したものと同一のものに
は同符号を付しである。Components in FIG. 1 that are the same as those shown in FIG. 2 are given the same reference numerals.
空間9,10および雨空間に連通する内外管の間隙に内
管8内圧力より高い約160KMCm2のHeを封入す
る。雨空間の1方(例えば上部空間9)に圧力計17を
連通させる。又、蒸気出側流路13及び液体す1〜リウ
ムの出側流路14にそれぞれ分析器15.16を連通さ
せる。Approximately 160 KMCm2 of He, which is higher than the internal pressure of the inner tube 8, is sealed in the gap between the inner and outer tubes communicating with the spaces 9 and 10 and the rain space. A pressure gauge 17 is connected to one side of the rain space (for example, the upper space 9). Further, analyzers 15 and 16 are connected to the vapor outlet channel 13 and the liquid solution outlet channels 14, respectively.
上記の如くづると、仮に内管8にクラックが入ると蒸気
圧J:すHe圧の方が高いので然気側に)(Cがリーク
し、He圧力が低下し、圧力計17ににリリーフしてい
るのが検出される。更に、分析器15によって蒸気中の
He濃度が増大するので内管8に損傷が生じたことが分
る。又、外管7にクラックが入ると同様にHeが液体す
1ヘリウム中に、リークし、He圧力が低下する。従っ
て、この場合も圧力計17によってリークしているのが
検出され、分析器16によって外管7が損傷しているの
が判る。According to the above, if a crack occurs in the inner tube 8, the vapor pressure J: (He pressure is higher, so it goes to the natural gas side) (C leaks, the He pressure decreases, and the pressure gauge 17 shows relief. Further, the analyzer 15 detects that the He concentration in the vapor increases, indicating that damage has occurred to the inner tube 8.Furthermore, if the outer tube 7 is cracked, the He concentration increases. leaks into the liquid helium, and the He pressure decreases.Therefore, in this case as well, the pressure gauge 17 detects the leak, and the analyzer 16 detects that the outer tube 7 is damaged. .
尚、圧力計ににる圧力変化の応答性をよくする為、内管
8の外面又は外管7の内面に軸心方向の溝を刻設しても
にり、内管、外管間の間隙を積極的に大きくしてもよい
。In addition, in order to improve the responsiveness of pressure changes on the pressure gauge, grooves in the axial direction may be carved on the outer surface of the inner tube 8 or the inner surface of the outer tube 7, so that the gap between the inner tube and the outer tube can be improved. The gap may be actively enlarged.
又、従来のものでは内管の肉厚は蒸気圧力に耐え得るだ
けの強度が必要であるし、外管も内管が11傷した場合
にも十分耐え得るだけの強度を必要とする。従って、伝
熱管が大径のものとなっていたが、本発明ではHeの圧
力を高くしており、内管8についてみれば内外周の差圧
は数+KMcm2のであり、内管はこの差圧に耐え1q
るだけの強度を有していればよい。In addition, in the conventional type, the inner tube needs to be thick enough to withstand steam pressure, and the outer tube needs to be strong enough to withstand even if the inner tube is damaged. Therefore, the heat transfer tube has a large diameter, but in the present invention, the pressure of He is increased, and when looking at the inner tube 8, the differential pressure between the inner and outer circumferences is several + KMccm2, and the inner tube has this differential pressure. withstands 1q
It is sufficient if the strength is as strong as the
尚、上記実施例に於いて伝熱管のリークのみを検出する
のであれば、分析器15.16は省略でき、リーク検出
シスデムの大幅な合理化につながる。In the above embodiment, if only leaks from the heat exchanger tubes are to be detected, the analyzers 15 and 16 can be omitted, leading to significant streamlining of the leak detection system.
[発明の効果]
以上述べた如く本発明によれば、伝熱管のリークが簡単
な装置で容易に検出し得、内管の肉厚を薄くできて、熱
伝達率の向上を図ることができると共に然気発生器を小
型にすることができる。[Effects of the Invention] As described above, according to the present invention, leaks in heat transfer tubes can be easily detected with a simple device, the wall thickness of the inner tube can be reduced, and the heat transfer coefficient can be improved. At the same time, the natural air generator can be made smaller.
第1図は本発明の説明図、第2図は従来例の説明図、第
3図は第2図のA部拡大図である。
6は2重伝熱管、7は外管、8は内管、17は圧力計を
示す。
第3図FIG. 1 is an explanatory diagram of the present invention, FIG. 2 is an explanatory diagram of a conventional example, and FIG. 3 is an enlarged view of section A in FIG. 6 is a double heat exchanger tube, 7 is an outer tube, 8 is an inner tube, and 17 is a pressure gauge. Figure 3
Claims (1)
流し、伝熱管内部に水を流して蒸気を発生させる2重管
蒸気発生器に於いて伝熱管の内管、外管の間に内管内圧
より高圧のヘリウムを封入し、該ヘリウムの圧力変化を
検知してリーク検出を行うことを特徴とする2重伝熱管
蒸気発生器のリーク検出方法。1) In a double-tube steam generator where the heat transfer tube is a double tube and liquid sodium is flowed outside the heat transfer tube and water is flowed inside the heat transfer tube to generate steam, there is a space between the inner and outer heat transfer tubes. A method for detecting leaks in a double heat exchanger tube steam generator, characterized in that helium is sealed at a pressure higher than the internal pressure of the inner tubes, and leaks are detected by detecting changes in the pressure of the helium.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61019457A JPS62177427A (en) | 1986-01-31 | 1986-01-31 | Leak detecting method for double heat conduction tube vapor generator |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61019457A JPS62177427A (en) | 1986-01-31 | 1986-01-31 | Leak detecting method for double heat conduction tube vapor generator |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS62177427A true JPS62177427A (en) | 1987-08-04 |
Family
ID=11999846
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP61019457A Pending JPS62177427A (en) | 1986-01-31 | 1986-01-31 | Leak detecting method for double heat conduction tube vapor generator |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS62177427A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2010071636A (en) * | 2008-09-17 | 2010-04-02 | Korea Atomic Energy Research Inst | Steam generator for sodium-cooled fast reactor having function of detecting breakage of heat transfer tube online |
CN106017817A (en) * | 2016-05-17 | 2016-10-12 | 中广核检测技术有限公司 | Secondary side system for helium mass spectrum leakage detection equipment for heat-transfer pipe of nuclear steam generator |
CN106092461A (en) * | 2016-05-17 | 2016-11-09 | 中广核检测技术有限公司 | Nuclear boiler heat-transfer pipe helium mass spectrum leak detection primary side purging system |
-
1986
- 1986-01-31 JP JP61019457A patent/JPS62177427A/en active Pending
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2010071636A (en) * | 2008-09-17 | 2010-04-02 | Korea Atomic Energy Research Inst | Steam generator for sodium-cooled fast reactor having function of detecting breakage of heat transfer tube online |
CN106017817A (en) * | 2016-05-17 | 2016-10-12 | 中广核检测技术有限公司 | Secondary side system for helium mass spectrum leakage detection equipment for heat-transfer pipe of nuclear steam generator |
CN106092461A (en) * | 2016-05-17 | 2016-11-09 | 中广核检测技术有限公司 | Nuclear boiler heat-transfer pipe helium mass spectrum leak detection primary side purging system |
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