KR20050007950A - Method for Preventing Corrosion in Tube sheet of Steam Generator - Google Patents
Method for Preventing Corrosion in Tube sheet of Steam Generator Download PDFInfo
- Publication number
- KR20050007950A KR20050007950A KR1020030047593A KR20030047593A KR20050007950A KR 20050007950 A KR20050007950 A KR 20050007950A KR 1020030047593 A KR1020030047593 A KR 1020030047593A KR 20030047593 A KR20030047593 A KR 20030047593A KR 20050007950 A KR20050007950 A KR 20050007950A
- Authority
- KR
- South Korea
- Prior art keywords
- tube sheet
- steam generator
- tube
- welding
- corrosion
- 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.)
- Withdrawn
Links
- 238000000034 method Methods 0.000 title claims abstract description 19
- 230000007797 corrosion Effects 0.000 title claims abstract description 18
- 238000005260 corrosion Methods 0.000 title claims abstract description 18
- 238000003466 welding Methods 0.000 claims abstract description 23
- 239000000463 material Substances 0.000 claims abstract description 7
- 238000005536 corrosion prevention Methods 0.000 claims abstract description 3
- 229910001098 inconels 690 Inorganic materials 0.000 abstract description 11
- 230000007547 defect Effects 0.000 abstract description 5
- 230000004907 flux Effects 0.000 abstract description 5
- 238000005253 cladding Methods 0.000 abstract description 4
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 230000033228 biological regulation Effects 0.000 description 1
- 229910052729 chemical element Inorganic materials 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 239000002075 main ingredient Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229910052759 nickel Inorganic materials 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
Landscapes
- Arc Welding In General (AREA)
Abstract
본 발명은, 원자력 증기발생기의 튜브 시트(tube sheet)에서 튜브가 삽입되는 평면 부위에서 고온과 진동에 의해 튜브 및 튜브 시트가 손상되고 부식이 발생되는 것을 막을 수 있는 부식 방지 방법에 관한 것이다.The present invention relates to a corrosion prevention method that can prevent the tube and the tube sheet from being damaged and the corrosion caused by the high temperature and vibration in the planar portion in which the tube is inserted in the tube sheet of the nuclear steam generator.
본 발명에 따르면, 원자력 발전소의 증기발생기에 구비되는 튜브 시트의 부식 방지 방법으로서, 고온에서 내부식성이 강한 재료의 스트립으로 상기 튜브 시트의 평면 부위를 덧씌우기 용접하는 단계 및 상기 덧씌우기 용접된 자리에 튜브 자리를 형성하는 단계로 구성되는 것을 특징으로 하는 증기발생기 튜브 시트의 부식 방지 방법이 제공된다.According to the present invention, there is provided a method for preventing corrosion of a tube sheet provided in a steam generator of a nuclear power plant, the method comprising: overlaying and welding a flat portion of the tubesheet with a strip of highly corrosion-resistant material at a high temperature; Provided is a method for preventing corrosion of a steam generator tube sheet, comprising the step of forming a tube seat.
본 발명에 의하면, 원자력 증기발생기의 튜브 시트 평면 부위에 덧씌우기(cladding) 용접을 인코넬 690스트립 및 플럭스 용접자재를 이용한 자동 용접 기법을 이용하여 작업 능률이 향상되고, 용접 결함이 축소되어 작업 시간 단축 등의 효과를 얻을 수 있다.According to the present invention, the welding efficiency of cladding on the tube sheet plane of the nuclear steam generator is improved by using an automatic welding technique using Inconel 690 strip and flux welding material, and the welding defect is reduced, thereby reducing the working time. And the like can be obtained.
Description
본 발명은, 원자력 증기발생기의 튜브 시트(tube sheet)에서 튜브가 삽입되는 평면 부위에서 고온과 진동에 의해 튜브 및 튜브 시트가 손상되고 부식이 발생되는 것을 막을 수 있는 부식 방지 방법에 관한 것이다.The present invention relates to a corrosion prevention method that can prevent the tube and the tube sheet from being damaged and the corrosion caused by the high temperature and vibration in the planar portion in which the tube is inserted in the tube sheet of the nuclear steam generator.
원자력 발전소에 구비되는 증기발생기에서, 튜브를 고정하는 튜브 시트의 평면 부위는 고온과 진동으로 인해 파손되고 부식되기 쉽다.In a steam generator provided in a nuclear power plant, the planar portion of the tube sheet for fixing the tube is easily broken and corroded by high temperature and vibration.
부식 문제를 해결하기 위하여 고온 내부식성이 우수한 니켈이 주성분인 인코넬690 소재를 이용하여 덧씌우기(cladding)를 한다. 종래에는 인코넬690 와이어를 이용한 용접 방법인 핫 티그 프로세스(hot TIG process)를 적용하여 증기발생기의 튜브 시트에 덧씌우기 작업을 수행하였다. 이 경우, 용착 효율이 저조하고, 용접부의 용접결함 및 건전성 등에 문제가 발생하였다.In order to solve the corrosion problem, cladding is performed using Inconel 690, which is a main ingredient of nickel, which has high temperature corrosion resistance. In the related art, a hot TIG process, which is a welding method using Inconel 690 wire, is applied to the tube sheet of the steam generator. In this case, the welding efficiency was low, and problems such as weld defects and soundness of the welded portion occurred.
본 발명은, 앞서 설명한 것과 같은 문제점을 해결하기 위해 개발된 것으로서, 본 발명의 목적은 용착 효율을 높일 수 있는 증기발생기 튜브 시트의 부식 방지 방법을 개발하는 것이다.The present invention has been developed to solve the problems as described above, the object of the present invention is to develop a method for preventing corrosion of the steam generator tube sheet that can increase the welding efficiency.
도 1은 증기발생기의 튜브 시트의 평면도.1 is a plan view of a tube sheet of a steam generator.
도 2는 도 1의 A-A 선을 따라 자른 단면도.2 is a cross-sectional view taken along the line A-A of FIG.
<도면의 주요 부분에 대한 부호의 설명><Explanation of symbols for the main parts of the drawings>
1: 튜브 시트 2, 2': 튜브 자리1: tube sheet 2, 2 ': tube seat
3: 용접 부분3: welding part
상기와 같은 본 발명의 목적은, 원자력 발전소의 증기발생기에 구비되는 튜브 시트의 부식 방지 방법으로서, 고온에서 내부식성이 강한 재료의 스트립으로 상기 튜브 시트의 평면 부위를 덧씌우기 용접하는 단계 및 상기 덧씌우기 용접된 자리에 튜브 자리를 형성하는 단계로 구성되는 증기발생기 튜브 시트의 부식 방지 방법을 제공함으로써 달성된다.An object of the present invention as described above, as a method for preventing corrosion of the tube sheet provided in the steam generator of the nuclear power plant, the step of overlay welding and welding the flat portion of the tube sheet with a strip of corrosion resistant material at high temperature It is achieved by providing a method for preventing corrosion of a steam generator tube sheet consisting of forming a tube seat in a pre-welded position.
이하, 첨부된 도면을 참조하여 본 발명의 바람직한 실시예를 상세하게 설명한다.Hereinafter, with reference to the accompanying drawings will be described in detail a preferred embodiment of the present invention.
도 1에는 증기발생기의 튜브 시트의 평면도가 도시되어 있고, 도 2에는 도 1의 A-A 선을 따라 자른 단면도가 도시되어 있다.1 is a plan view of a tube sheet of a steam generator, and FIG. 2 is a cross-sectional view taken along the line A-A of FIG.
도 1에 도시된 것과 같이, 증기발생기의 튜브 시트(1)에는 튜브가 삽입되어 고정될 수 있는 튜브 자리(2)가 다수 형성되어 있다.As shown in Figure 1, the tube sheet (1) of the steam generator is formed with a plurality of tube seats (2) to which the tube can be inserted and fixed.
도 2에 도시된 것과 같이, 본 발명에 의한 증기발생기 튜브 시트의 부식 방지 방법에서는 상기 튜브 자리(2)가 다수 형성되어 있는 평면 부위에 최소 3단으로 덧씌우기 작업을 수행한다. 덧씌우기 작업은 와이어가 아닌 스트립을 사용하여 잠호용접(Submerged Arc Welding: SAW) 공정으로 수행된다. 상기 스트립은 고온 내부식성이 우수한 인코넬 690 스트립을 사용하고, 잠호용접에 사용되는 플럭스 또한 고온 내부식성이 우수한 인코넬 690 재질을 사용한다.As shown in FIG. 2, in the method for preventing corrosion of the steam generator tube sheet according to the present invention, a covering operation is performed in at least three stages on a flat portion in which a plurality of tube seats 2 are formed. Overlaying is performed in a submerged arc welding (SAW) process using strips rather than wires. The strip uses Inconel 690 strip having excellent high temperature corrosion resistance, and the flux used for latent welding also uses Inconel 690 material having high temperature corrosion resistance.
용접 균열에 영향을 끼치는 주요 화학원소인 Mn, Cr 및 Ti의 함유량을 적용 발명규격 혹은 코우드(code) 규제치 범위 이내에서 다음과 같이 관리하여 사용한다. 즉, 함유량이 증가할수록 결함길이가 증가하는 Cr의 함유량을 인코넬690의 규격 범위인 28.0 내지 31.5(중량%, 이하 같음) 사이에서 최대 30.79로 제한하고, 함유량이 증가할수록 결함길이가 감소하는 Mn의 함유량을 인코넬690의 규격 범위인 5.0 이하에서 최소 2.76으로 제한하며, 함유량이 증가할수록 결함길이가 감소하는 Ti의 함유량을 인코넬690의 규격 범위인 0.50 이하에서 최소 0.09로 제한한다. 본 함유량에 대한 제한 범위는 스트립과 플럭스 모두에 적용된다.The contents of Mn, Cr and Ti, which are the major chemical elements affecting the welding crack, are controlled and used within the scope of the applied invention or code regulation as follows. That is, as the content increases, the content of Cr, which increases the defect length, is limited to a maximum of 30.79 in the range of 28.0 to 31.5 (weight% or less), which is the standard range of Inconel 690, and as the content increases, The content is limited to a minimum of 2.76 in the Inconel 690 specification range of 5.0 or less, and the content of Ti, which decreases the defect length as the content increases, is limited to the minimum of 0.09 in the Inconel 690 specification range of 0.50 or less. The limiting range for this content applies to both strips and fluxes.
용접이 완료되면, 용접 부분(3)에 튜브 자리(2')를 다시 형성하여 튜브 시트의 부식 방지 구조를 완성한다.When the welding is completed, the tube seat 2 'is again formed in the welded portion 3 to complete the corrosion protection structure of the tube sheet.
본 인코넬 690 스트립과 플럭스 용접자재를 이용한 용접 프로세스는 튜브 시트(tube sheet)의 평면 부위의 덧씌우기(cladding) 용접 기법 뿐만 아니라, 원자로압력용기(shell)나 헤드(head)의 인코넬 690 버터링(buttering) 용접 부위에도 발명 적용이 가능하다.The welding process using Inconel 690 strips and flux welding materials is not only a cladding welding technique for planar sections of tube sheets, but also Inconel 690 buttering of reactor pressure shells or heads. ) The invention can be applied to the welded part.
본 발명에 의하면, 원자력 증기발생기의 튜브 시트 평면 부위에 덧씌우기(cladding) 용접을 인코넬 690스트립 및 플럭스 용접자재를 이용한 자동 용접 기법을 이용하여 작업 능률이 향상되고, 용접 결함이 축소되어 작업 시간 단축 등의 효과를 얻을 수 있다.According to the present invention, the work of the cladding welding on the tube sheet plane of the nuclear steam generator is improved by using the automatic welding technique using Inconel 690 strip and flux welding material, and the welding defect is reduced and the working time is shortened. And the like can be obtained.
이상에서는 본 발명의 특정의 바람직한 실시예에 대하여 도시하고 또한 설명하였다. 그러나, 본 발명은 상술한 실시예에 한정되지 아니하며, 특허청구의 범위에서 청구하는 본 발명의 요지를 벗어남이 없이 당해 발명이 속하는 기술분야에서 통상의 지식을 가진 자라면 누구든지 다양한 변형실시가 가능할 것이다.In the above, certain preferred embodiments of the present invention have been illustrated and described. However, the present invention is not limited to the above-described embodiments, and various modifications can be made by those skilled in the art without departing from the gist of the present invention as claimed in the claims. will be.
Claims (1)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
KR1020030047593A KR20050007950A (en) | 2003-07-12 | 2003-07-12 | Method for Preventing Corrosion in Tube sheet of Steam Generator |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
KR1020030047593A KR20050007950A (en) | 2003-07-12 | 2003-07-12 | Method for Preventing Corrosion in Tube sheet of Steam Generator |
Publications (1)
Publication Number | Publication Date |
---|---|
KR20050007950A true KR20050007950A (en) | 2005-01-21 |
Family
ID=37221250
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
KR1020030047593A Withdrawn KR20050007950A (en) | 2003-07-12 | 2003-07-12 | Method for Preventing Corrosion in Tube sheet of Steam Generator |
Country Status (1)
Country | Link |
---|---|
KR (1) | KR20050007950A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103629655A (en) * | 2012-08-20 | 2014-03-12 | 韩国水力原子力 | Tube sheet of steam generator having anticorrosive layer and manufacturing method thereof |
KR20170014315A (en) | 2015-07-29 | 2017-02-08 | (주) 성부 | Tube sheet of tube type heat exchanger and method for manufacturing the same |
KR200490861Y1 (en) | 2018-07-06 | 2020-02-11 | 두산중공업 주식회사 | Apparatus for cleaning steam generator tube sheet |
KR20200001780U (en) | 2019-01-30 | 2020-08-07 | 두산중공업 주식회사 | Strip welding head |
-
2003
- 2003-07-12 KR KR1020030047593A patent/KR20050007950A/en not_active Withdrawn
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103629655A (en) * | 2012-08-20 | 2014-03-12 | 韩国水力原子力 | Tube sheet of steam generator having anticorrosive layer and manufacturing method thereof |
CN103629655B (en) * | 2012-08-20 | 2016-01-27 | 韩国水力原子力 | Steam generator tube sheet with anticorrosive coat and preparation method thereof |
US9341367B2 (en) | 2012-08-20 | 2016-05-17 | Korea Hydro & Nuclear Power Co., Ltd. | Tube sheet of steam generator having anticorrosive layer and manufacturing method thereof |
KR20170014315A (en) | 2015-07-29 | 2017-02-08 | (주) 성부 | Tube sheet of tube type heat exchanger and method for manufacturing the same |
KR200490861Y1 (en) | 2018-07-06 | 2020-02-11 | 두산중공업 주식회사 | Apparatus for cleaning steam generator tube sheet |
KR20200001780U (en) | 2019-01-30 | 2020-08-07 | 두산중공업 주식회사 | Strip welding head |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
JPS5989902A (en) | Repair of sleeve type of damaged nuclear power steam generator pipe | |
US8217295B2 (en) | Method for producing a welded connection for use in a corrosive environment | |
EP2678130B1 (en) | Weld overlay structure and a method of providing a weld overlay structure | |
JP5978633B2 (en) | Manufacturing method of water-cooled wall panel | |
KR101518155B1 (en) | Welding structure and welding method | |
JP2002242696A5 (en) | ||
JP4915251B2 (en) | Clad welded structure of low alloy steel base metal | |
KR20050007950A (en) | Method for Preventing Corrosion in Tube sheet of Steam Generator | |
JP2017121656A (en) | Welding method, and welding member structure | |
JPH0557450A (en) | Method for welding dissimilar metal | |
EP1493968B1 (en) | Membrane wall | |
JP4350490B2 (en) | Anti-corrosion structure with corrosion-resistant thin metal sheet | |
Zhang et al. | All-positional flux cored wire with lower trace element contents and improved ambient temperature toughness for welding P91 steels | |
JP2009248095A (en) | WELDING METHOD USING Ni-BASED WELDING MATERIAL | |
JPH08152290A (en) | Method for welding different metals and welded structure thereof | |
JPS63199075A (en) | How to weld metal pipes | |
JP2001252781A (en) | Connection method of clad steel | |
JP2006088226A (en) | Welding of vessel internals with noble metal technology | |
JP2005152994A (en) | Welding coating method of corrosion-resistant thin metal sheet on thick metal substrate surface | |
KR20240109457A (en) | Method of connecting reactor nozzle and pipe in nuclear power plant | |
JP2010234418A (en) | Structure of different material joint and method for manufacturing different material joint | |
JP6672898B2 (en) | Boiler tube reinforcement device and boiler tube reinforcement method | |
JPH08152291A (en) | Welding structure of tube to header and welding method | |
KR100380289B1 (en) | fixed structure for nozzle sleeve | |
JPS597483A (en) | One side welding method of high purity ferritic stainless clad steel |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PA0109 | Patent application |
Patent event code: PA01091R01D Comment text: Patent Application Patent event date: 20030712 |
|
PG1501 | Laying open of application | ||
PC1203 | Withdrawal of no request for examination | ||
WITN | Application deemed withdrawn, e.g. because no request for examination was filed or no examination fee was paid |