KR910003859Y1 - Device detecting eddy current in atomic power plant - Google Patents
Device detecting eddy current in atomic power plant Download PDFInfo
- Publication number
- KR910003859Y1 KR910003859Y1 KR2019880021339U KR880021339U KR910003859Y1 KR 910003859 Y1 KR910003859 Y1 KR 910003859Y1 KR 2019880021339 U KR2019880021339 U KR 2019880021339U KR 880021339 U KR880021339 U KR 880021339U KR 910003859 Y1 KR910003859 Y1 KR 910003859Y1
- Authority
- KR
- South Korea
- Prior art keywords
- power plant
- eddy current
- heat pipe
- device detecting
- steam generator
- Prior art date
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Investigating Or Analyzing Materials By The Use Of Magnetic Means (AREA)
Abstract
내용 없음.No content.
Description
제 1 도는 본 고안의 탐촉자가 적용되는 증기 발생기의 일부를 절대한 사시도.1 is an absolute perspective view of a part of a steam generator to which the transducer of the present invention is applied.
제 2 도는 본 고안 탐촉자의 일부를 절단한 구조도.2 is a structural diagram cut a part of the probe of the present invention.
본 고안은 원자력 발전소의 원자력발전소 증기발생기의 전열관의 와전류를 효과적으로 탐상되게하는 탐촉자의 개량에 관한 것이다.The present invention relates to an improvement of a probe for effectively detecting the eddy current of a heat pipe of a nuclear power plant steam generator of a nuclear power plant.
원자력 발저소에서는 안정성을 확보하기 위하여 일전한 증기 마다 비파괴검사를 실시하는데 이들 검사들은 신속하고 정확하게 실시하는 것이 매우 중요하다.At the nuclear site, nondestructive tests are performed on every steam to ensure stability. It is very important that these tests be carried out quickly and accurately.
또한 결함의 검출이 용이해야하고 검사시간을 단축할 수 있는 검사장비가 개발된다면 전력회사의 운영비를 많이 절약할 수 있는 것이다.In addition, the development of inspection equipment that should be easy to detect defects and shorten the inspection time can save a lot of utilities' operating costs.
본 고안의 탐촉자는 이와같은 목적을 가지는 통상의 탐촉자가 가지는 결점을 보완하기 위하여 탐촉자가 전열관중 "" 형 튜브를 통과할 때 쉽게 휘어지고 또 복귀특성을 우수하게 하기위한 몇가지 구조를 개량한 것으로서 그 요지를 첨부도면에 연관시켜 상세히 설명하면 다음과 같다.The transducer of the present invention is designed to compensate for the shortcomings of a conventional transducer having such a purpose. "It is an improvement of several structures to easily bend when passing through a mold tube and excellent return characteristics.
원자력발전소 증기발생기(1)의 직선 전열관(2) 및 곡선절열관(3)내부를 통과 하면서 전열관의 결함을 검출하는 탐촉자 어셈블리(A)에 있어서, 탄두형 멘드릴(4)와 하단브래킷(5)사이에 곡면(R)이 형성된 마디(6)(6')를 끼우고 그 중앙에 전열관의 크기와 결함 검출에 좋은 주파수에 맞게 감은 코일(7)을 설치하고 그 상하에 브러쉬(8)(8')를 설치하여 하단브래킷(5)아래에 휨특성이 좋게 이음여유를 준 구조의 플레시블 호오스(9)를 연결시킨 구조 이다.In the transducer assembly (A) for detecting defects of the heat pipe while passing through the inside of the straight heat pipe (2) and the curved heat pipe (3) of the nuclear power plant steam generator (1), the warhead-type mandrel (4) and the bottom bracket (5) Between the nodes (6) and (6 ') with curved surface (R) formed between them, and install coils (7) wound around the center to the size of the heat pipe and good frequency for defect detection. 8 ') is installed under the lower bracket (5) to connect the flexible hose (9) of the structure with a flexible margin with good bending characteristics.
미설명부호 10은 전선이다.Reference numeral 10 is a wire.
이와같이된 본 고안의 탐촉자는 어셈블리(A)가 증기발생기(1)의 직선 전열관(2) 및 곡선전열관(3)의 내부를 통과하면서 코일(7)이 와전류를 발생시켜 전열관의 결함을 외부에서 탐상하는 것인데 특히 "" 튜브인곡선 전열관(3)을 통과할때는 본 고안의 탐촉자는 여러개의 마디(6)(6')가 곡면(R)이 형성되어 있어서 마찰 저항이 적고 복귀 특성이 좋으며 브러쉬(8)(8')는 코일 (7)이 전열관의 중앙에 위치하도록 정열시켜주며 플레시블 호오스99)는 각마디의 여유가 있는 휨과 복귀 특성이 좋은 구조 임으로 검사 도중에 꺽었을 때 쉽게 복귀되어 탐촉자를 교체하거나 바로 잡을 필요가 없어 검사시간을 단축 하는 것이다.In this way, the probe of the present invention has an assembly (A) passing through the inside of the linear heat pipe (2) and the curved heat pipe (3) of the steam generator (1), the coil (7) generates an eddy current to detect the defect of the heat pipe from the outside In particular, "When passing through the tube-curved heat pipe (3), the probe of the present invention has a number of nodes (6) (6 ') with a curved surface (R), so it has low frictional resistance, good return characteristics, and a brush (8) (8'). ) Is arranged so that the coil (7) is located in the center of the heat pipe, and the flexible hose (99) has a good bending and returning characteristic of each node, so it is easily returned when it is bent during the inspection to replace or correct the transducer. There is no need to shorten the inspection time.
그러므로 본 고안은 몇 개의 간결한 구조개량 으로서 엄격한 안전성이 요구되는 원자력 발전소 설비를 신속 정확 하게 탐상할 수 있어서 안전도 향상과 유지비의 절감에 기여하는 2중 효과가 있는 것이다.Therefore, the present invention has a double effect of contributing to the improvement of safety and the reduction of maintenance cost because it can quickly and accurately inspect the nuclear power plant equipment which requires strict safety with several simple structural improvements.
Claims (1)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| KR2019880021339U KR910003859Y1 (en) | 1988-12-23 | 1988-12-23 | Device detecting eddy current in atomic power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| KR2019880021339U KR910003859Y1 (en) | 1988-12-23 | 1988-12-23 | Device detecting eddy current in atomic power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| KR900013272U KR900013272U (en) | 1990-07-05 |
| KR910003859Y1 true KR910003859Y1 (en) | 1991-06-03 |
Family
ID=19282436
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| KR2019880021339U KR910003859Y1 (en) | 1988-12-23 | 1988-12-23 | Device detecting eddy current in atomic power plant |
Country Status (1)
| Country | Link |
|---|---|
| KR (1) | KR910003859Y1 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100696991B1 (en) * | 2006-01-25 | 2007-03-20 | 한국원자력연구소 | Apparatus and method for searching eddy current of electric heat tube using measuring magnetic permeability in steam generator |
-
1988
- 1988-12-23 KR KR2019880021339U patent/KR910003859Y1/en not_active IP Right Cessation
Also Published As
| Publication number | Publication date |
|---|---|
| KR900013272U (en) | 1990-07-05 |
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