CN111318851B - Repair method for fillet weld of manhole neck joint of pressure vessel in nuclear power plant - Google Patents
Repair method for fillet weld of manhole neck joint of pressure vessel in nuclear power plant Download PDFInfo
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- CN111318851B CN111318851B CN202010283605.1A CN202010283605A CN111318851B CN 111318851 B CN111318851 B CN 111318851B CN 202010283605 A CN202010283605 A CN 202010283605A CN 111318851 B CN111318851 B CN 111318851B
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- 238000000034 method Methods 0.000 title claims abstract description 25
- 238000003466 welding Methods 0.000 claims abstract description 90
- 239000000463 material Substances 0.000 claims abstract description 44
- 238000011179 visual inspection Methods 0.000 claims abstract description 41
- 238000007689 inspection Methods 0.000 claims abstract description 31
- 239000007788 liquid Substances 0.000 claims abstract description 28
- 238000005498 polishing Methods 0.000 claims abstract description 17
- 238000011049 filling Methods 0.000 claims abstract description 16
- 230000007547 defect Effects 0.000 claims abstract description 14
- 238000001514 detection method Methods 0.000 claims abstract description 11
- 241001016380 Reseda luteola Species 0.000 claims description 36
- 239000002893 slag Substances 0.000 claims description 14
- 238000002161 passivation Methods 0.000 claims description 12
- 239000003086 colorant Substances 0.000 claims description 10
- 229910001220 stainless steel Inorganic materials 0.000 claims description 8
- 230000003647 oxidation Effects 0.000 claims description 6
- 238000007254 oxidation reaction Methods 0.000 claims description 6
- 230000035515 penetration Effects 0.000 claims description 6
- 239000010935 stainless steel Substances 0.000 claims description 6
- 239000011148 porous material Substances 0.000 claims description 5
- 239000002253 acid Substances 0.000 claims description 3
- 238000005554 pickling Methods 0.000 claims description 3
- 210000003739 neck Anatomy 0.000 description 11
- 208000037656 Respiratory Sounds Diseases 0.000 description 4
- 229910000831 Steel Inorganic materials 0.000 description 4
- 230000008595 infiltration Effects 0.000 description 4
- 238000001764 infiltration Methods 0.000 description 4
- 239000002184 metal Substances 0.000 description 4
- 239000013049 sediment Substances 0.000 description 4
- 239000010959 steel Substances 0.000 description 4
- 230000000694 effects Effects 0.000 description 2
- 239000012530 fluid Substances 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 210000002445 nipple Anatomy 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- 229910000975 Carbon steel Inorganic materials 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 239000010962 carbon steel Substances 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 230000007717 exclusion Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000009659 non-destructive testing Methods 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23P—METAL-WORKING NOT OTHERWISE PROVIDED FOR; COMBINED OPERATIONS; UNIVERSAL MACHINE TOOLS
- B23P6/00—Restoring or reconditioning objects
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Abstract
The invention discloses a method for repairing a fillet weld of a manhole neck joint of a pressure vessel in a nuclear power plant, which comprises the following steps: polishing a welding line in the nuclear pressure container; carrying out first visual inspection on the barrel side and the adapter side mother material, and carrying out first liquid permeation inspection; if the first visual inspection and the first liquid permeation inspection are qualified, performing internal welding filling; polishing a welding seam outside the nuclear pressure vessel; carrying out secondary visual inspection on the parent material at the cylinder side, the connecting pipe side and the root of the welding line, and carrying out secondary liquid permeation inspection; if the second visual inspection and the second liquid permeation inspection are qualified, performing external welding filling; and carrying out volume type detection on the whole circle of welding seam. The repair method can eliminate all weld defects and avoid the problem of assembly welding again after the manhole connecting pipe is integrally taken out.
Description
Technical Field
The invention relates to the technical field of nuclear pressure vessels, in particular to a repair method for fillet welds of manhole connecting necks of pressure vessels in a nuclear power plant.
Background
The lower part of the barrel 1 of the nuclear pressure vessel is provided with a manhole 2. The manhole cover 3 and the cylinder 1 are connected by a fillet (hereinafter referred to as a manhole cover fillet) as shown in fig. 1. During the daily operation of the nuclear pressure vessel, UT (ultrasonic flaw detection) inspection finds that the whole circle inside the fillet weld of the manhole neck of the nuclear pressure vessel has volume type defects, and the potential of developing penetrating cracks exists in long-term operation, so that the leakage risk exists.
Aiming at the defect, the conventional treatment method is to cut and take out the manhole adapter pipe from the cylinder body integrally along a welding line by using a flame cutting mode, then polish the surfaces of the parent material at the side of the cylinder body and the side of the adapter pipe by using an angle grinder to remove all welding flesh, thereby completely eliminating the defect, and finally, carrying out assembly welding again. However, this method has the following problems:
1. flame cutting is only suitable for carbon steel containers (part of defective containers are made of stainless steel);
2. when the manhole connecting pipe is reassembled and assembled, the positioning of the manhole connecting pipe is difficult to keep consistent with the design, and certain deviation exists;
3. when the manhole connecting pipe is reassembled and assembled, the manhole connecting pipe is difficult to center and fix;
4. because need polish after the whole cutting of manhole takeover and get rid of the barrel side and take over the whole flesh that welds of side, the clearance between barrel and the takeover can grow on the whole, and this can cause welding filling volume grow, welding deformation and stress corresponding increase.
In addition, because the grinding is performed manually, a local gap may be too large, which may adversely affect the welding. Defects such as cracks and unfused weld roots can occur, thereby increasing the risk of leakage.
The information disclosed in this background section is only for enhancement of understanding of the general background of the invention and should not be taken as an acknowledgement or any form of suggestion that this information forms the prior art already known to a person skilled in the art.
Disclosure of Invention
The invention aims to provide a repair method for fillet welds of a manhole neck of a pressure vessel of a nuclear power plant, which can not only completely eliminate weld defects, but also avoid the problem of re-assembly welding after the integral manhole connecting pipe is taken out.
In order to achieve the aim, the invention provides a repair method for a fillet weld of a manhole neck joint of a pressure vessel of a nuclear power plant, which comprises the following steps: polishing a welding line in the nuclear pressure container; carrying out first visual inspection on the barrel side and the adapter side mother material, and carrying out first liquid permeation inspection; if the first visual inspection and the first liquid permeation inspection are qualified, performing internal welding filling; polishing a welding seam outside the nuclear pressure vessel; carrying out secondary visual inspection on the parent material at the cylinder side, the connecting pipe side and the root of the welding line, and carrying out secondary liquid permeation inspection; if the second visual inspection and the second liquid permeation inspection are qualified, performing external welding filling; and carrying out volume type detection on the whole circle of welding seam formed after the internal welding filling and the external welding filling, and determining to be qualified.
In an embodiment of the present invention, the rework method for nuclear power plant pressure vessel manhole neck fillet weld further comprises the following steps: if the nuclear pressure vessel is made of stainless steel, carrying out acid pickling passivation on the whole welding line after carrying out volume type detection on the whole welding line; and performing a third visual inspection of the state of the surface passivation film, the weld and the heat affected zone.
In one embodiment of the present invention, the third visual inspection comprises: and confirming whether the surface passivation film is uniform or not, whether the stripes with uneven colors exist or not and whether the welding seams and the heat affected zones have oxidation colors or not, wherein if the surface passivation film is uniform and has no stripes with uneven colors and the welding seams and the heat affected zones have no oxidation colors, the third visual inspection is qualified.
In one embodiment of the invention, when the weld is ground in the nuclear pressure vessel, the grinding depth is at least 1/2 of the wall thickness of the vessel by taking the inner surface of the nuclear pressure vessel as a reference, so that the weld on the cylinder side and the connecting pipe side is completely removed.
In one embodiment of the invention, when the welding seam is ground on the outer part of the nuclear pressure vessel, the grinding depth is at least 1/2 of the wall thickness of the vessel by taking the outer surface of the nuclear pressure vessel as a reference, so as to reach the root of the inner newly welded welding seam, and the welding seam on the cylinder side and the connecting pipe side is completely removed.
In one embodiment of the present invention, the first visual inspection of the barrel-side and nipple-side parent stock comprises: visual inspection barrel side and whether take over side mother material have crackle, gas pocket, inclusion sediment or arc pit, and liquid infiltration inspection for the first time includes: and (5) checking whether the parent materials on the cylinder side and the connecting pipe side exceed the standard or not.
In one embodiment of the invention, if the parent metal on the cylinder side and the connecting pipe side does not have cracks, air holes, slag inclusion or craters, and the parent metal on the cylinder side and the connecting pipe side does not exceed the standard, the first visual inspection and the first liquid permeation inspection are qualified; if the parent material at the cylinder side and the connecting pipe side has cracks, air holes, slag inclusions or craters, or the parent material at the cylinder side and the connecting pipe side has overproof display, the grinding is continued until the overproof defect is eliminated.
In one embodiment of the present invention, the second visual inspection of the barrel-side and nozzle-side parent stock and the root of the weld comprises: visual inspection barrel side and whether take over side mother material and welding seam root have crackle, gas pocket, clamp sediment or arc pit, and the liquid infiltration inspection of second time includes: and (5) checking whether the parent materials on the cylinder side and the connecting pipe side and the root of the welding line exceed the standard or not.
In one embodiment of the invention, if the barrel side, the connecting pipe side mother material and the welding seam root have no cracks, pores, slag or craters, and the barrel side, the connecting pipe side mother material and the welding seam root have no overproof display, the second visual inspection and the second liquid permeation inspection are qualified; if cracks, air holes, slag or arc pits exist at the barrel side, the connecting pipe side mother material and the welding seam root, or the barrel side, the connecting pipe side mother material and the welding seam root are displayed in an overproof mode, the barrel side, the connecting pipe side mother material and the welding seam root are polished continuously until the overproof defect is eliminated.
Compared with the prior art, the repair method for the fillet weld of the manhole neck of the pressure vessel in the nuclear power plant has the following advantages: the repair method comprises the steps of firstly polishing the welding seam inside the nuclear pressure container until the welding seam is qualified through detection, then welding and filling, polishing the welding seam outside the container until the welding seam is qualified through detection, and then carrying out volume type detection on the whole welding seam to confirm that the welding seam is qualified. The method does not need to integrally cut and take out the manhole connecting pipe, thereby avoiding various problems during the reassembling welding, ensuring the forming quality of welding seams and providing powerful support for the safe and reliable operation of a nuclear power unit.
Drawings
FIG. 1 is a schematic illustration of a nuclear power plant pressure vessel manhole location according to an embodiment of the present invention;
FIG. 2 is a flow chart of a rework method for a nuclear power plant pressure vessel manhole neck fillet weld according to an embodiment of the invention.
Detailed Description
The following detailed description of the present invention is provided in conjunction with the accompanying drawings, but it should be understood that the scope of the present invention is not limited to the specific embodiments.
Throughout the specification and claims, unless explicitly stated otherwise, the word "comprise", or variations such as "comprises" or "comprising", will be understood to imply the inclusion of a stated element or component but not the exclusion of any other element or component.
As shown in fig. 2, the repair method for the fillet weld of the manhole neck of the nuclear power plant pressure vessel according to the preferred embodiment of the invention comprises the following steps: step 101 is performed: and polishing the welding line in the nuclear pressure vessel. The tools used for polishing are an angle polishing machine, a vernier caliper, a steel plate ruler and a steel wire brush (the stainless steel nuclear pressure container needs to use the stainless steel wire brush). Then, step 102 is performed: the barrel side and nipple side stock were subjected to a first visual inspection and a first liquid penetration inspection. If both the first visual inspection and the first liquid penetrant inspection are acceptable, then step 103 is performed: and performing internal welding filling. Then, step 104 is performed: and polishing the welding seam outside the nuclear pressure vessel. The tools used for polishing are an angle polishing machine, a vernier caliper, a steel plate ruler and a steel wire brush (the stainless steel nuclear pressure container needs to use the stainless steel wire brush). Then, step 105 is performed: and carrying out secondary visual inspection on the barrel side, the connecting pipe side mother material and the root of the welding line, and carrying out secondary liquid permeation inspection. If both the second visual inspection and the second liquid penetrant inspection are acceptable, then step 106 is performed: and carrying out external welding filling. Finally, step 107 is performed: and carrying out volume type detection on the whole circle of welding seam formed after the internal welding filling and the external welding filling, and confirming to be qualified.
It should be noted that the first fluid penetrant inspection and the second fluid penetrant inspection of the present invention both use penetrant test criteria: NB/T47013.5-2015 (see section 5 of nondestructive testing of pressure bearing equipment: penetration testing).
In an embodiment of the present invention, the rework method for nuclear power plant pressure vessel manhole neck fillet weld further comprises the following steps: if the nuclear pressure vessel is made of stainless steel, carrying out acid pickling passivation on the whole circle of welding line after volume type detection; and carrying out third visual inspection on the states of the surface passivation film, the welding seam and the heat affected zone, and confirming the conditions to be qualified.
In one embodiment of the present invention, the third visual inspection comprises: and confirming whether the surface passivation film is uniform or not, whether the stripes with uneven colors exist or not and whether the welding seams and the heat affected zones have oxidation colors or not, wherein if the surface passivation film is uniform and has no stripes with uneven colors and the welding seams and the heat affected zones have no oxidation colors, the third visual inspection is qualified.
In one embodiment of the invention, when the weld is ground in the nuclear pressure vessel, the grinding depth is at least 1/2 of the wall thickness of the vessel by taking the inner surface of the nuclear pressure vessel as a reference so as to ensure that the weld on the cylinder side and the connecting pipe side is completely removed.
In one embodiment of the invention, when the welding seam is ground on the outer part of the nuclear pressure vessel, the grinding depth is at least 1/2 of the wall thickness of the vessel by taking the outer surface of the nuclear pressure vessel as a reference, and the welding seam on the cylinder side and the connecting pipe side is completely removed based on reaching the root of the newly welded welding seam on the inner part.
In one embodiment of the present invention, the step 102 of performing a first visual inspection of the barrel side and the nipple side mother material includes: visual inspection barrel side and whether take over side mother material have crackle, gas pocket, inclusion sediment or arc pit, and liquid infiltration inspection for the first time includes: and (5) checking whether the parent materials on the cylinder side and the connecting pipe side exceed the standard or not.
In one embodiment of the present invention, if the barrel side and the nozzle side parent metal do not have cracks, pores, slag inclusions or craters, and the barrel side and the nozzle side parent metal do not show an excessive indication (the root of the weld is not qualified and has no effect), the first visual inspection and the first liquid penetration inspection are passed. If the parent material of the cylinder side and the connecting pipe side has cracks, air holes, slag inclusions or craters, or the parent material of the cylinder side and the connecting pipe side exceeds the standard, the step 201 is carried out: and continuously polishing until the standard exceeding defect is eliminated.
In one embodiment of the present invention, the performing the second visual inspection of the barrel side and the nozzle side parent material and the root of the weld in step 105 includes: visual inspection barrel side and whether take over side mother material and welding seam root have crackle, gas pocket, clamp sediment or arc pit, and the liquid infiltration inspection of second time includes: and (5) checking whether the parent materials on the cylinder side and the connecting pipe side and the root of the welding line exceed the standard or not.
In one embodiment of the present invention, if there is no crack, air hole, slag or crater in the barrel side and the nozzle side parent material and the root of the weld, and there is no indication of excessive exceeding in the barrel side and the nozzle side parent material and the root of the weld, the second visual inspection and the second liquid penetration inspection are passed. If cracks, air holes, slag inclusions or arc pits exist at the barrel side, the connecting pipe side mother material and the welding seam root, or the barrel side, the connecting pipe side mother material and the welding seam root exceed the standard, the step 202 is carried out: and continuously polishing until the standard exceeding defect is eliminated.
The repair method for the fillet weld of the manhole neck joint of the pressure vessel in the nuclear power plant can not only eliminate all weld defects, but also avoid the problem of recoupling and welding after the manhole connecting pipe is integrally taken out. The repair method is used on site at present, has a good use effect, effectively promotes the treatment of site defects, ensures the forming quality of welding seams, and provides a strong support for the safe and reliable operation of a nuclear power unit.
The foregoing descriptions of specific exemplary embodiments of the present invention have been presented for purposes of illustration and description. It is not intended to limit the invention to the precise form disclosed, and obviously many modifications and variations are possible in light of the above teaching. The exemplary embodiments were chosen and described in order to explain certain principles of the invention and its practical application to enable one skilled in the art to make and use various exemplary embodiments of the invention and various alternatives and modifications as are suited to the particular use contemplated. It is intended that the scope of the invention be defined by the claims and their equivalents.
Claims (7)
1. A repair method for fillet weld of a manhole neck of a pressure vessel in a nuclear power plant is characterized by comprising the following steps:
polishing a welding line in the nuclear pressure container;
carrying out first visual inspection on the barrel side and the adapter side mother material of the nuclear pressure vessel, and carrying out first liquid permeation inspection;
if the first visual inspection and the first liquid permeation inspection are qualified, performing internal welding filling;
polishing the welding line outside the nuclear pressure vessel;
carrying out a second visual inspection on the cylinder side, the connecting pipe side mother material and the welding seam root, and carrying out a second liquid permeation inspection;
if the second visual inspection and the second liquid permeation inspection are qualified, performing external welding filling; and
carrying out volume type detection on the whole circle of welding seam formed after the internal welding filling and the external welding filling, and determining that the welding seam is qualified;
when welding seams are ground in the nuclear pressure vessel, the grinding depth is at least 1/2 of the wall thickness of the vessel by taking the inner surface of the nuclear pressure vessel as a reference, so that welding seams on the barrel side and the connecting pipe side are all removed;
when the welding seam is ground outside the nuclear pressure vessel, 1/2 with the depth being at least the wall thickness of the vessel is ground by taking the outer surface of the nuclear pressure vessel as a reference so as to reach the root of the welding seam newly welded inside and completely remove the welding seam on the cylinder side and the connecting pipe side.
2. A method of reworking a fillet weld for a nuclear power plant pressure vessel manhole neck as recited in claim 1, further comprising the steps of:
if the nuclear pressure vessel is made of stainless steel, carrying out acid pickling passivation on the whole circle of welding line after carrying out volume type detection on the whole circle of welding line; and
and carrying out third visual inspection on the states of the surface passivation film, the welding seam and the heat affected zone of the whole circle of welding seam.
3. A rework method for nuclear power plant pressure vessel manhole neck fillet weld of claim 2, wherein the third visual inspection comprises:
confirming whether the surface passivation film is uniform or not, whether the stripes with non-uniform colors exist or not and whether the welding seams and the heat affected zones have oxidation colors or not;
wherein if the surface passivation film is uniform and has no uneven spots of color, and the weld and the heat affected zone have no oxidation color, the third visual inspection is qualified.
4. A method of reworking a nuclear power plant pressure vessel manhole neck fillet weld according to claim 1, wherein said first visual inspection of the barrel side and the nozzle side parent stock comprises: visually inspecting the barrel side and the adapter side mother material for cracks, pores, slag inclusions or craters, wherein the first liquid penetration inspection comprises: and checking whether the parent materials on the barrel side and the connecting pipe side exceed the standard or not to display.
5. The method for repairing a fillet weld of a manhole and a neck of a nuclear power plant pressure vessel as claimed in claim 4, wherein if the parent materials of the barrel side and the connecting pipe side do not have cracks, pores, slag inclusions or craters and the parent materials of the barrel side and the connecting pipe side do not exceed standards, the first visual inspection and the first liquid permeation inspection are qualified; and if the parent materials of the cylinder side and the connecting pipe side have cracks, air holes, slag inclusions or craters, or the parent materials of the cylinder side and the connecting pipe side have overproof display, continuing polishing until the overproof defect is eliminated.
6. A method of reworking a nuclear power plant pressure vessel manhole neck fillet weld according to claim 1, wherein said second visual inspection of the barrel side and nozzle side parent stock and weld root comprises: visually inspecting whether the barrel side, the connecting pipe side mother material and the welding seam root have cracks, air holes, slag inclusion or arc pits or not, wherein the second liquid permeation inspection comprises the following steps: and checking whether the parent materials on the cylinder side and the connecting pipe side and the welding seam root exceed the standard or not.
7. The method for repairing a fillet weld of a manhole and a neck of a nuclear power plant pressure vessel as claimed in claim 6, wherein if the root of the weld and the parent materials on the barrel side and the connecting pipe side do not have cracks, pores, slag or craters, and the root of the weld and the parent materials on the barrel side and the connecting pipe side do not exceed standards, the second visual inspection and the second liquid penetration inspection are qualified; if cracks, air holes, slag or arc pits exist at the barrel side, the connecting pipe side mother material and the welding seam root, or the barrel side, the connecting pipe side mother material and the welding seam root are displayed in an overproof mode, the barrel side, the connecting pipe side mother material and the welding seam root are polished continuously until the overproof defect is eliminated.
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| CN112045364A (en) * | 2020-08-25 | 2020-12-08 | 上海核工程研究设计院有限公司 | Method for repairing J-shaped welding seam of pressure boundary of nuclear-grade small-diameter penetration piece |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102126062A (en) * | 2011-01-07 | 2011-07-20 | 蓬莱巨涛海洋工程重工有限公司 | Secondary repair process method of high-strength steel welds |
| CN104308449A (en) * | 2014-08-28 | 2015-01-28 | 天津市管道工程集团有限公司 | Technology for repairing big-caliber concrete pipeline lining by utilizing thin wall stainless steel |
| CN105710594A (en) * | 2014-12-03 | 2016-06-29 | 重庆远煌机械制造有限公司 | Repairing process for welds of fixed roof storage tank |
| CN108032033A (en) * | 2017-12-06 | 2018-05-15 | 中国航发沈阳黎明航空发动机有限责任公司 | A kind of restorative procedure of turborotor cold air hole crackle |
| CN109454397A (en) * | 2018-10-23 | 2019-03-12 | 岳阳大陆激光技术有限公司 | A kind of restorative procedure of drum type vacuum filter filler cylinder |
| CN109702427A (en) * | 2019-01-25 | 2019-05-03 | 重庆工业职业技术学院 | A method for repairing the corrosion part of the original composite layer of the tank body |
| CN110052728A (en) * | 2019-05-14 | 2019-07-26 | 安徽马钢设备检修有限公司 | A kind of online welding repair method of Ball Milling Machine End Cover cracking |
| CN110340619A (en) * | 2019-07-17 | 2019-10-18 | 攀钢集团钛业有限责任公司 | Crack Repair Method for Stainless Steel Furnace Cover |
-
2020
- 2020-04-13 CN CN202010283605.1A patent/CN111318851B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102126062A (en) * | 2011-01-07 | 2011-07-20 | 蓬莱巨涛海洋工程重工有限公司 | Secondary repair process method of high-strength steel welds |
| CN104308449A (en) * | 2014-08-28 | 2015-01-28 | 天津市管道工程集团有限公司 | Technology for repairing big-caliber concrete pipeline lining by utilizing thin wall stainless steel |
| CN105710594A (en) * | 2014-12-03 | 2016-06-29 | 重庆远煌机械制造有限公司 | Repairing process for welds of fixed roof storage tank |
| CN108032033A (en) * | 2017-12-06 | 2018-05-15 | 中国航发沈阳黎明航空发动机有限责任公司 | A kind of restorative procedure of turborotor cold air hole crackle |
| CN109454397A (en) * | 2018-10-23 | 2019-03-12 | 岳阳大陆激光技术有限公司 | A kind of restorative procedure of drum type vacuum filter filler cylinder |
| CN109702427A (en) * | 2019-01-25 | 2019-05-03 | 重庆工业职业技术学院 | A method for repairing the corrosion part of the original composite layer of the tank body |
| CN110052728A (en) * | 2019-05-14 | 2019-07-26 | 安徽马钢设备检修有限公司 | A kind of online welding repair method of Ball Milling Machine End Cover cracking |
| CN110340619A (en) * | 2019-07-17 | 2019-10-18 | 攀钢集团钛业有限责任公司 | Crack Repair Method for Stainless Steel Furnace Cover |
Non-Patent Citations (3)
| Title |
|---|
| 压力容器缺陷的检测及修补实例;印明奎;《石油化工设备》;19840425(第04期);第82-83页 * |
| 尿素CO_2吸收塔异种钢角焊缝的修复;杨文广等;《焊接》;20011031(第10期);第42-43页 * |
| 杨文广等.尿素CO_2吸收塔异种钢角焊缝的修复.《焊接》.2001,(第10期), * |
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