CN105234573A - Method and system for damage repair of tube plate and caulk weld of steam generator of nuclear power station - Google Patents
Method and system for damage repair of tube plate and caulk weld of steam generator of nuclear power station Download PDFInfo
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- CN105234573A CN105234573A CN201510741931.1A CN201510741931A CN105234573A CN 105234573 A CN105234573 A CN 105234573A CN 201510741931 A CN201510741931 A CN 201510741931A CN 105234573 A CN105234573 A CN 105234573A
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K31/00—Processes relevant to this subclass, specially adapted for particular articles or purposes, but not covered by only one of the preceding main groups
- B23K31/02—Processes relevant to this subclass, specially adapted for particular articles or purposes, but not covered by only one of the preceding main groups relating to soldering or welding
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K31/00—Processes relevant to this subclass, specially adapted for particular articles or purposes, but not covered by only one of the preceding main groups
- B23K31/12—Processes relevant to this subclass, specially adapted for particular articles or purposes, but not covered by only one of the preceding main groups relating to investigating the properties, e.g. the weldability, of materials
- B23K31/125—Weld quality monitoring
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K2101/00—Articles made by soldering, welding or cutting
- B23K2101/04—Tubular or hollow articles
- B23K2101/14—Heat exchangers
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Abstract
The invention discloses a method and a system for damage repair of a tube plate and a caulk weld of a steam generator of a nuclear power station, and solves the technical problem that a conventional SG site repair technology cannot completely eliminate the influence of foreign object damage on SG. The method comprises the following steps: S1, conducting foreign object damage inspection on the tube plate and the caulk weld to obtain damage inspection data; S2, calculating the damage inspection data to obtain damage calculation data of the tube plate and the caulk weld; S3, conducting damage repair on the tube plate and the caulk weld based on the damage calculation data; and S4, after damage repair is finished, conducting repair inspection on the tube plate and the caulk weld to ensure that the repaired tube plate and the repaired caulk weld meet the equipment code requirement. Through the adoption of the method and the system, that the size of the repaired caulk weld meets the requirement is ensured, and a hardened layer and a stress corrosion risk can be eliminated.
Description
Technical field
The present invention relates to foreign matter under pressurized-water reactor nuclear power plant primary Ioops environment to steam generator tube sheet and caulk weld (flush configuration) technology for repairing damaged field, particularly relate to a kind of nuclear power station steam generator tube sheet and caulk weld damage rehabilitation method and system.
Background technology
Pressurized-water reactor nuclear power plant primary Ioops capital equipment comprises reactor pressure vessel, main pipeline, steam generator (SG, SteamGenerator), main pump, voltage-stablizer etc., as shown in Figure 1, SG is separated for primary side 21 and secondary side 22 by tube sheet 1, primary side 21 is separated for primary side hot hydroecium 211 and primary side cold water chamber 212 by hydroecium dividing plate 20, U-shaped heat-transfer pipe 3 is provided with in secondary side 22, two ends of heat-transfer pipe 3 are communicated with primary side cold water chamber 212 with primary side hot hydroecium 211 respectively through tube sheet 1, in Fig. 1, arrow shows the flow route of cooling agent in SG inside, concrete, reactor coolant is after reactor pressure vessel absorbs the heat of fuel kernel reaction, SG primary side hot hydroecium 211 is entered through main pipe hot leg, cold section of main pipeline is entered by SG primary side cold water chamber 212 afterwards after heat-transfer pipe 3 is by the water cooling in secondary side 22, by main pump, it is pressed into reactor pressure vessel again.
As shown in Figure 2, for SG tube to tube-sheet welds schematic diagram, pipe refers to U-shaped heat-transfer pipe 3 in Fig. 1, tube sheet vial sheetpile layer (i.e. tube sheet 1 in Fig. 1), tube to tube-sheet welds refers to the attachment weld of heat transfer tube hydroforming overlay cladding, weldering larynx refers to the minimum range of root of weld O point to face of weld, and fusion penetration refers to the vertical range of root of weld O point to tube sheet overlay surface.In the stages such as manufacture, installation, in-service maintenances, all there is the possibility that foreign matter is mixed into primary Ioops, under primary Ioops fluid matasomatism: for tiny foreign matter, any position of primary Ioops may be entered, even enter other system; For slightly larger foreign matter (larger than heat-transfer pipe internal diameter), due to the restriction of heat-transfer pipe internal diameter, make it stay SG hydroecium inner, repeatedly clash into tube sheet and caulk weld, major injury is caused to it.Every platform SG is provided with a large amount of heat-transfer pipes, heat-transfer pipe end is concordant with tube sheet overlay cladding, caulk weld is formed from molten by TIG, caulk weld size is very little, the design of presurized water reactor nuclear islands equipment and construction rule (i.e. RCC-M) requirement to tube to tube-sheet welds weldering larynx size are: mean value is not less than 0.9e, and minimum of a value is not less than 0.66e, wherein, e is heat-transfer pipe wall thickness, nominal size e=1.09mm.From size, foreign matter clashes into the pit formed can cause remarkable impact to caulk weld; In addition, foreign matter clashes into the impact also bringing sclerosis and stress corrosion aspect.Therefore, to the caulk weld of large-area tube sheet and large quantity, the reparation eliminating above-mentioned foreign object damage impact completely becomes an industry difficult problem.
Through investigation, existingly occurred repeatedly SG foreign object damage case, in these cases, some pipes and tube sheet syndeton are that pipe protrudes tube sheet format surface, damage location is mainly the tube end of protrusion, and the repair mode taked is the excision of impaired tube end or corrects; Certainly pipe, tube sheet flush configuration SG is also had to damage case, but substantially all occur in the operation phase, due to the reason that radiation protection etc. is many, generally do not repair or simply repair and directly run, arrange the preparation carrying out SG replacing, also have generation before runtime, degree of injury is relatively light simultaneously, eliminated hardened layer and the stress corrosion risk of tube sheet overlay cladding by polishing reparation, but can not ensure that caulk weld size meets the demands.
In sum, existing SG field repair technology cannot eliminate the impact of foreign object damage on SG equipment completely.
Summary of the invention
The present invention is directed to existing SG field repair technology and cannot eliminate the technical problem of foreign object damage on the impact of SG equipment completely, provide a kind of nuclear power station steam generator tube sheet and caulk weld damage rehabilitation method and system, can ensure that the caulk weld size after repairing meets the demands, and hardened layer and stress corrosion risk can be eliminated.
On the one hand, embodiments provide a kind of nuclear power station steam generator tube sheet and caulk weld damage rehabilitation method, described caulk weld is fixedly connected with tube sheet and the heat-transfer pipe of described steam generator, described damage is that foreign matter clashes into described tube sheet and described caulk weld forms, and described restorative procedure comprises step:
S1, foreign object damage inspection is carried out to described tube sheet and described caulk weld, to obtain damage check data;
S2, computing is carried out to described damage check data, to obtain the damage measurement process data of described tube sheet and described caulk weld;
S3, based on described damage measurement process data, injury repair is carried out to described tube sheet and described caulk weld;
S4, after described injury repair completes, to described tube sheet and described caulk weld carry out reparation inspection.
Optionally, described step S1 is specially:
Inspection obtains the pit depth described tube sheet being clashed into the affected area formed by foreign matter, and inspection obtain described caulk weld clashed into by foreign matter after weldering larynx size and caulk weld spout diameter.
Optionally, described step S2 is specially:
Based on described damage check data, Size calculation process, stress corrosion computing and the computing of In-service testing feasibility are carried out to described tube sheet and described caulk weld, to obtain damage measurement process data.
Optionally, described step S3 is specially:
Based on described damage measurement process data, described tube sheet and described caulk weld are welded and polish reparation.
Optionally, described step S2 specifically comprises:
The thickness that the pit depth of the affected area of described tube sheet and described tube sheet overlay cladding dispatched from the factory compares, the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is greater than the first preset value is the first affected area, and the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is less than or equal to described first preset value is the second affected area;
Obtain and the chromium constituent content of the affected area of described tube sheet and the second preset value are compared, determine that the affected area that chromium constituent content is less than the described tube sheet of described second preset value is the 3rd affected area, the surface of described 3rd affected area is tensile stress state;
Detect on described tube sheet overlay cladding and there is part that is sharp-pointed or groove, and described part that is sharp-pointed or groove is defined as the 4th affected area;
Weldering larynx size after being clashed into by foreign matter by described caulk weld and presurized water reactor nuclear islands equipment design and build rule request and compare, determine automatic surfacing layer welds larynx size and be less than or equal to that the caulk weld of the 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is less than or equal to the 5th preset value be the 4th affected area, and determine automatic surfacing layer welds larynx size and be greater than that the caulk weld of described 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is greater than described 4th preset value be the 6th affected area;
Obtain and the chromium constituent content of the affected area of described caulk weld and described second preset value are compared, determine that the chromium constituent content of the affected area of the caulk weld on automatic surfacing layer is greater than described second preset value, and the affected area surface of caulk weld on automatic surfacing layer is tensile stress state, and determine that the chromium constituent content of affected area of the caulk weld on manual build up welding layer is less than described second preset value, and the affected area surface of caulk weld on manual build up welding layer is tensile stress state;
Described caulk weld spout diameter and the 5th preset value are compared, determines that the caulk weld mouth of pipe that spout diameter is less than described 5th preset value is the 7th affected area.
Optionally, described step S3 specifically comprises:
Polishing reparation is carried out to described first affected area, REPAIR WELDING is carried out to described second affected area;
Described 3rd affected area is polished, to make the roughness on the affected area surface after polishing be less than or equal to the 6th preset value, and then makes the 3rd affected area surface after polishing change into compressive stress state by tensile stress state;
Rounding off process is carried out to described 4th affected area, primary Ioops radioactive liquid residual on described tube sheet during to reduce In-service testing;
Overhead welding reparation is carried out to described 5th affected area and fills up metal; Carry out polishing reparation to described 6th affected area, be less than or equal to described 6th preset value with the roughness on the caulk weld surface after making polishing reparation, the 6th affected area surface after repairing of guaranteeing to polish is compressive stress state;
Described 7th affected area is polished, to make described spout diameter be greater than described 5th preset value, and then enables eddy current probe through the described caulk weld mouth of pipe.
Optionally, described step S4 is specially:
Outward appearance detection, liquid penetration examination, size detection and ultrasound detection are carried out to the described tube sheet after repairing, outward appearance detection, liquid penetration examination, size detection and ray detection are carried out to the described caulk weld after repairing, stress test and the water pressure test are carried out to the described tube sheet after reparation and described caulk weld entirety.
On the other hand, the embodiment of the present invention additionally provides a kind of nuclear power station steam generator tube sheet and caulk weld injury repair system, described caulk weld is fixedly connected with tube sheet and the heat-transfer pipe of described steam generator, described damage is that foreign matter clashes into described tube sheet and described caulk weld forms, and described repair system comprises:
Damage inspection module, for carrying out foreign object damage inspection to described tube sheet and described caulk weld, to obtain damage check data;
Damage measurement processing module, for carrying out computing to described damage check data, to obtain the damage measurement process data of described tube sheet and described caulk weld;
Injury repair module, for carrying out injury repair based on described damage measurement process data to described tube sheet and described caulk weld;
Repair inspection module, for after described injury repair completes, reparation inspection is carried out to described tube sheet and described caulk weld.
Optionally, described damage inspection module specifically for:
Inspection obtains the pit depth described tube sheet being clashed into the affected area formed by foreign matter, and inspection obtain described caulk weld clashed into by foreign matter after weldering larynx size and caulk weld spout diameter.
Optionally, described damage measurement processing module specifically for:
Based on described damage check data, Size calculation process, stress corrosion computing and the computing of In-service testing feasibility are carried out to described tube sheet and described caulk weld, to obtain damage measurement process data.
Optionally, described injury repair module specifically for:
Based on described damage measurement process data, described tube sheet and described caulk weld are welded and polish reparation.
Optionally, described damage measurement processing module comprises:
Tubesheet dimension calculation processing unit, compare for the pit depth of the affected area by described tube sheet and the described tube sheet overlay cladding thickness that dispatches from the factory, the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is greater than the first preset value is the first affected area, and the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is less than or equal to described first preset value is the second affected area;
Tube sheet stress corrosion calculation processing unit, for obtaining and the chromium constituent content of the affected area of described tube sheet and the second preset value being compared, determine that the affected area that chromium constituent content is less than the described tube sheet of described second preset value is the 3rd affected area, the surface of described 3rd affected area is tensile stress state;
, there is part that is sharp-pointed or groove for detecting on described tube sheet overlay cladding, and described part that is sharp-pointed or groove be defined as the 4th affected area in the in-service feasibility calculation processing unit of tube sheet;
Caulk weld Size calculation processing unit, design and build rule request for the weldering larynx size after being clashed into by foreign matter by described caulk weld and presurized water reactor nuclear islands equipment to compare, determine automatic surfacing layer welds larynx size and be less than or equal to that the caulk weld of the 4th preset value and manual build up welding layer to weld the caulk weld that larynx size is less than or equal to the 5th preset value be the 5th affected area, and determine automatic surfacing layer welds larynx size and be greater than that the caulk weld of described 4th preset value and manual build up welding layer to weld the caulk weld that larynx size is greater than described 5th preset value be the 6th affected area,
Caulk weld stress corrosion calculation processing unit, for obtaining and the chromium constituent content of the affected area of described caulk weld and described second preset value being compared, determine that the chromium constituent content of the affected area of the caulk weld on automatic surfacing layer is greater than described second preset value, and the affected area surface of caulk weld on automatic surfacing layer is tensile stress state, and determine that the chromium constituent content of affected area of the caulk weld on manual build up welding layer is less than described second preset value, and the affected area surface of caulk weld on manual build up welding layer is tensile stress state;
The in-service feasibility calculation processing unit of caulk weld, for described caulk weld spout diameter and the 6th preset value being compared, determines that the caulk weld mouth of pipe that spout diameter is less than described 6th preset value is the 7th affected area.
Optionally, described injury repair module comprises:
Unit repaired by tube sheet, for carrying out polishing reparation to described first affected area, carries out REPAIR WELDING to described second affected area; Also for polishing to described 3rd affected area, to make the roughness on the affected area surface after polishing be less than or equal to the 3rd preset value, and then the 3rd affected area surface after polishing is made to change into compressive stress state by tensile stress state; And for carrying out rounding off process to described 4th affected area, primary Ioops radioactive liquid residual on described tube sheet during to reduce In-service testing;
Caulk weld repairs unit, fills up metal for carrying out overhead welding reparation to described 5th affected area; Carry out polishing reparation to described 6th affected area, be less than or equal to described 3rd preset value with the roughness on the caulk weld surface after making polishing reparation, the 6th affected area surface after repairing of guaranteeing to polish is compressive stress state; Also for polishing to described 7th affected area, to make described spout diameter be greater than described 5th preset value, and then enable eddy current probe through the described caulk weld mouth of pipe.
Optionally, described reparation inspection module specifically for:
Outward appearance detection, liquid penetration examination, size detection and ultrasound detection are carried out to the described tube sheet after repairing, outward appearance detection, liquid penetration examination, size detection and ray detection are carried out to the described caulk weld after repairing, stress test and the water pressure test are carried out to the described tube sheet after reparation and described caulk weld entirety.
One or more technical scheme provided by the invention, at least has following technique effect or advantage:
Due in the present invention, propose a whole set of recovery technique for steam generator tube sheet and caulk weld damage, comprising: foreign object damage inspection is carried out to described tube sheet and described caulk weld, to obtain damage check data; Computing is carried out to described damage check data, to obtain the damage measurement process data of described tube sheet and described caulk weld; Based on described damage measurement process data, injury repair is carried out to described tube sheet and described caulk weld; And after described injury repair completes, reparation inspection is carried out to described tube sheet and described caulk weld, to guarantee that the described tube sheet after repairing and described caulk weld meet equipment code requirement.Efficiently solve existing SG field repair technology and cannot eliminate the technical problem of foreign object damage on the impact of SG equipment completely, can ensure that the caulk weld size after repairing meets the demands, and hardened layer and stress corrosion risk can be eliminated.
Accompanying drawing explanation
In order to be illustrated more clearly in the embodiment of the present invention or technical scheme of the prior art, be briefly described to the accompanying drawing used required in embodiment or description of the prior art below, apparently, accompanying drawing in the following describes is only embodiments of the invention, for those of ordinary skill in the art, under the prerequisite not paying creative work, other accompanying drawing can also be obtained according to the accompanying drawing provided.
Fig. 1 to circulate schematic diagram for nuclear power plant reactor cooling agent that background technology of the present invention provides in steam generator;
The nuclear power station steam generator pipe that Fig. 2 provides for background technology of the present invention and panel weld schematic diagram;
A kind of nuclear power station steam generator tube sheet that Fig. 3 provides for the embodiment of the present invention and caulk weld damage rehabilitation method flow chart;
A kind of nuclear power station steam generator pipe that Fig. 4 provides for the embodiment of the present invention and tube plate welding structure schematic diagram;
A kind of nuclear power station steam generator tube sheet that Fig. 5 A provides for the embodiment of the present invention and caulk weld injury repair system architecture diagram;
The another kind of nuclear power station steam generator tube sheet that Fig. 5 B provides for the embodiment of the present invention and caulk weld injury repair system architecture diagram.
Detailed description of the invention
The embodiment of the present invention is by providing a kind of nuclear power station steam generator tube sheet and caulk weld damage rehabilitation method, solve existing SG field repair technology and cannot eliminate the technical problem of foreign object damage on the impact of SG equipment completely, achieve the caulk weld size after reparation to meet the demands, and the technique effect of hardened layer and stress corrosion risk can be eliminated.
The technical scheme of the embodiment of the present invention is for solving the problems of the technologies described above, and general thought is as follows:
Embodiments provide a kind of nuclear power station steam generator tube sheet and caulk weld damage rehabilitation method, described caulk weld is fixedly connected with tube sheet and the heat-transfer pipe of described steam generator, described damage is that foreign matter clashes into described tube sheet and described caulk weld forms, described restorative procedure comprises step: S1, carry out foreign object damage inspection to described tube sheet and described caulk weld, to obtain damage check data; S2, computing is carried out to described damage check data, to obtain the damage measurement process data of described tube sheet and described caulk weld; S3, based on described damage measurement process data, injury repair is carried out to described tube sheet and described caulk weld; S4, after described injury repair completes, to described tube sheet and described caulk weld carry out reparation inspection.
Visible, in embodiments of the present invention, a whole set of recovery technique is proposed for steam generator tube sheet and caulk weld damage, efficiently solve existing SG field repair technology and cannot eliminate the technical problem of foreign object damage on the impact of SG equipment completely, can ensure that the caulk weld size after repairing meets the demands, and hardened layer and stress corrosion risk can be eliminated.
In order to better understand technique scheme, below in conjunction with Figure of description and concrete embodiment, technique scheme is described in detail, the specific features being to be understood that in the embodiment of the present invention and embodiment is the detailed description to technical scheme, instead of the restriction to technical scheme, when not conflicting, the technical characteristic in the embodiment of the present invention and embodiment can combine mutually.
Embodiment one
Please refer to Fig. 3, embodiments provide a kind of nuclear power station steam generator tube sheet and caulk weld damage rehabilitation method, described caulk weld is fixedly connected with tube sheet and the heat-transfer pipe of described steam generator, described damage is that foreign matter clashes into described tube sheet and described caulk weld forms, and described restorative procedure comprises step:
S1, foreign object damage inspection is carried out to described tube sheet and described caulk weld, to obtain damage check data;
S2, computing is carried out to described damage check data, to obtain the damage measurement process data of described tube sheet and described caulk weld;
S3, based on described damage measurement process data, injury repair is carried out to described tube sheet and described caulk weld;
S4, after described injury repair completes, to described tube sheet and described caulk weld carry out reparation inspection, with guarantee repair after described tube sheet and described caulk weld meet equipment code requirement.
Visible, above-mentioned steps S1 is damage checking procedure, and above-mentioned steps S2 is damage measurement treatment step, and above-mentioned steps S3 is injury repair step, and above-mentioned steps S4 is for repairing checking procedure.
In specific implementation process, described step S1 is specially: inspection obtains the pit depth described tube sheet being clashed into the affected area formed by foreign matter, and inspection obtain described caulk weld clashed into by foreign matter after weldering larynx size (namely welding surplus size on larynx path) and caulk weld spout diameter; Wherein, the affected area of described tube sheet can be multiple, and the pit depth of each affected area can not be identical.Described step S2 is specially: carry out Size calculation process, stress corrosion computing and the computing of In-service testing feasibility based on described damage check data to described tube sheet and described caulk weld, to obtain damage measurement process data.Described step S3 is specially: to weld and polish reparation to described tube sheet and described caulk weld based on described damage measurement process data.
In specific implementation process, for above-mentioned damage measurement treatment step S2, it specifically comprises:
1) Size calculation process is carried out to tube sheet: the thickness that the pit depth of the affected area of described tube sheet and described tube sheet overlay cladding dispatched from the factory compares, the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is greater than the first preset value is the first affected area, and the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is less than or equal to described first preset value is the second affected area; Wherein, described first preset value value is 8mm.
2) stress corrosion computing is carried out to tube sheet: obtain and chromium element (chemical element expression symbol the is Cr) content of the affected area of described tube sheet and the second preset value compared, determine that the affected area that chromium constituent content is less than the described tube sheet of described second preset value is the 3rd affected area, the surface of described 3rd affected area is tensile stress state; Wherein, described second preset value is 24%.Concrete, tube sheet stress corrosion is mainly relevant to environment, material, stress three elements; Wherein, " environment " is primary Ioops water environment, will not analyze; " material " mostly is Ni-Cr-Fe alloy, for Ni-Cr-Fe alloy, existing scientific achievement and engineering experience all show: if it is greater than 24% containing Cr amount, stress corrosion can not occur, if it is less than or equal to 24% containing Cr amount, then there is the possibility that stress corrosion occurs.For China's nuclear power station two generation project, tube sheet overlay cladding generally adopts 82/182 type Nickel-based Alloy Welding material, 24% is less than containing Cr amount, in tube sheet surface stress, non-perished surface is compressive stress state (stress corrosion can not occur), perished surface is tensile stress state (stress corrosion can occur), concrete, as shown in Figure 4, for the Welding Structure schematic diagram between tube sheet 41 and pipe 42 (i.e. heat-transfer pipe), according to different positions, tube sheet overlay cladding comprises automatic surfacing (specifically can be automatic strip surfacing) layer 421 and manual build up welding layer 422, automatic surfacing layer 421 wlding adopts 82 alloys, manual build up welding layer 422 wlding adopts 182 alloys, tube sheet overlay cladding divides different parts wlding different, Cr content is all different, but be all less than 24%, therefore computing is needed to determine the affected area of described tube sheet and repair it, compressive stress state is changed into by tensile stress state to make affected area.
3) computing of In-service testing feasibility is carried out to tube sheet: detect on described tube sheet overlay cladding and there is part that is sharp-pointed or groove, and described part that is sharp-pointed or groove is defined as the 4th affected area;
4) Size calculation process is carried out to tube-tube plate caulk weld: the weldering larynx size after being clashed into by foreign matter by described caulk weld and presurized water reactor nuclear islands equipment design and build rule (i.e. RCC-M) and require to compare, determine automatic surfacing layer welds larynx size and be less than or equal to that the caulk weld of the 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is less than or equal to the 4th preset value be the 5th affected area, and determine automatic surfacing layer welds larynx size and be greater than that the caulk weld of described 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is greater than described 4th preset value be the 6th affected area, wherein, described 3rd preset value is 0.66e+ δ, and described 4th preset value is 0.66e+ δ, e be pipe 42 wall thickness be 1.09mm, δ is that metrical error can value 0.04mm.
5) stress corrosion computing is carried out to tube-tube plate caulk weld: obtain and the chromium constituent content of the affected area of described caulk weld and described second preset value (namely 24%) compared, determine that the chromium constituent content of the affected area of the caulk weld on automatic surfacing layer is greater than described second preset value, and the affected area surface of caulk weld on automatic surfacing layer is tensile stress state, and determine that the chromium constituent content of affected area of the caulk weld on manual build up welding layer is less than described second preset value, and the affected area surface of caulk weld on manual build up welding layer is tensile stress state, concrete, caulk weld is the hybrid metal after tube sheet overlay cladding and heat-transfer pipe melt, therefore Cr content can be different, still please refer to Fig. 4, automatic surfacing layer 421 wlding adopts 82 alloys, manual build up welding layer 422 wlding adopts 182 alloys, pipe 42 adopts 690 alloys, tube-tube plate caulk weld 43 on automatic surfacing layer 421 is 690/82 alloy fusion metal, 24% is greater than containing Cr amount, tube-tube plate caulk weld 44 (being positioned at hydroecium dividing plate 45 both sides of SG) on manual build up welding layer 422 is 690/182 alloy fusion metal, 24% is less than containing Cr amount, impaired caulk weld on manual overlay cladding 422 need be repaired, compressive stress state is changed into by tensile stress state to make its surface.
6) computing of In-service testing feasibility is carried out to tube-tube plate caulk weld: described caulk weld spout diameter and the 5th preset value are compared, determine that the caulk weld mouth of pipe that spout diameter is less than described 5th preset value is the 7th affected area; Wherein, described 5th preset value is 16.60
+ 0.05mm.Concrete, the in-service stage need carry out eddy-current test, and when carrying out EDDY CURRENT, detection probe need by heat-transfer pipe, and therefore the internal diameter of heat-transfer pipe is wanted to allow probe to pass through, and now requires that the internal diameter of heat-transfer pipe is more than or equal to 16.60
+ 0.05mm, could allow process of popping one's head in, but produces projection because foreign matter shock may cause heat transfer mouth of pipe metal to be squeezed, and cause eddy current probe to pass through, when needing to repair, spout diameter is more than or equal to 16.60
+ 0.05mm.
Further, above-mentioned injury repair step S3 specifically comprises:
(1) injury repair is carried out to tube sheet:
Polishing reparation is carried out to described first affected area, REPAIR WELDING is carried out to described second affected area; Described 3rd affected area is polished, to make the roughness on the affected area surface after polishing be less than or equal to the 6th preset value, and then makes the 3rd affected area surface after polishing change into compressive stress state by tensile stress state; Rounding off process (namely can be grinding process) is carried out to described 4th affected area, primary Ioops radioactive liquid residual on described tube sheet during to reduce In-service testing, and then reduce the dose of radiation that reviewer is subject to; Wherein, described 6th preset value can value be 6.3um.Polish repair time, adopt overall polishing to large area repair, the degree of depth is not more than (fusion penetration-0.9e), fails restoring area adopt detail sanding to entirety polishing, polishing repair after surface roughness be not more than 6.3um.
(2) injury repair is carried out to tube-tube plate caulk weld:
Overhead welding reparation is carried out to described 5th affected area and fills up metal, notice that solder technology should be able to meet on-the-spot narrow and small closed space, and the impact that secondary side exists steam should be able to be eliminated.Polishing reparation is carried out to described 6th affected area, all sharp-pointed, the recess region of rounding off, be less than or equal to described 6th preset value (i.e. 6.3um) with the roughness on the caulk weld surface after making polishing reparation, the 6th affected area surface after repairing of guaranteeing to polish is compressive stress state.Described 7th affected area is polished, is greater than described 5th preset value (namely 16.60 to make described spout diameter
+ 0.05and then enable eddy current probe through the described caulk weld mouth of pipe mm).In addition, the caulk weld that polishing internal diameter does not meet the demands, makes it to meet the demands.
Further, described step S4 is specially:
Outward appearance detection, liquid penetration examination, size detection and ultrasound detection are carried out to the described tube sheet after repairing, outward appearance detection, liquid penetration examination, size detection and ray detection are carried out to the described caulk weld after repairing, stress test and the water pressure test are carried out to the described tube sheet after reparation and described caulk weld entirety, to guarantee that the described tube sheet after repairing and described caulk weld meet equipment code requirement.Wherein, carry out size detection to the described tube sheet after repairing and be specially and carry out thickness measuring to Zone R 46 as shown in Figure 4, ultrasound detection is for carry out thickness measuring to non-Zone R; Carrying out size detection to the described caulk weld after reparation is that spout diameter detects, and ray detection is for detect REPAIR WELDING.
This recovery technique is mainly for the inner foreign matter impact damage of the SG before labour, and this damage is mainly mixed into foreign matter due to the primary Ioops test before labour, thus to the damage that evaporimeter causes under liquid flow effect.Certain nuclear power projects SG foreign object damage domestic at present have employed field repair technology of the present invention, eliminate hardened layer and stress corrosion risk, surface stress measurement result is compression, and caulk weld size meets the demands, the disposable examination that have passed the water pressure test.Through the checking of actual items, field repair technology of the present invention eliminates hardened layer and stress corrosion risk, ensure that caulk weld size, achieves good effect.
Embodiment two
Based on same inventive concept, please refer to Fig. 5 A, the embodiment of the present invention additionally provides a kind of nuclear power station steam generator tube sheet and caulk weld injury repair system, described caulk weld is fixedly connected with tube sheet and the heat-transfer pipe of described steam generator, described damage is that foreign matter clashes into described tube sheet and described caulk weld forms, and described repair system comprises:
Damage inspection module 51, for carrying out foreign object damage inspection to described tube sheet and described caulk weld, to obtain damage check data;
Damage measurement processing module 52, for carrying out computing to described damage check data, to obtain the damage measurement process data of described tube sheet and described caulk weld;
Injury repair module 53, for carrying out injury repair based on described damage measurement process data to described tube sheet and described caulk weld;
Repair inspection module 54, for after described injury repair completes, reparation inspection is carried out to described tube sheet and described caulk weld, to guarantee that the described tube sheet after repairing and described caulk weld meet equipment code requirement.
In specific implementation process, described damage inspection module 51 specifically for:
Inspection obtains the pit depth described tube sheet being clashed into the affected area formed by foreign matter, and inspection obtain described caulk weld clashed into by foreign matter after weldering larynx size and caulk weld spout diameter.
In specific implementation process, described damage measurement processing module 52 specifically for:
Based on described damage check data, Size calculation process, stress corrosion computing and the computing of In-service testing feasibility are carried out to described tube sheet and described caulk weld, to obtain damage measurement process data.
In specific implementation process, described injury repair module 53 specifically for:
Based on described damage measurement process data, described tube sheet and described caulk weld are welded and polish reparation.
In specific implementation process, please refer to Fig. 5 B, described damage measurement processing module 52 comprises:
Tubesheet dimension calculation processing unit 521, compare for the pit depth of the affected area by described tube sheet and the described tube sheet overlay cladding thickness that dispatches from the factory, the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is greater than the first preset value is the first affected area, and the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is less than or equal to described first preset value is the second affected area;
Tube sheet stress corrosion calculation processing unit 522, for obtaining and the chromium constituent content of the affected area of described tube sheet and the second preset value being compared, determine that the affected area that chromium constituent content is less than the described tube sheet of described second preset value is the 3rd affected area, the surface of described 3rd affected area is tensile stress state;
, there is part that is sharp-pointed or groove for detecting on described tube sheet overlay cladding, and described part that is sharp-pointed or groove be defined as the 4th affected area in the in-service feasibility calculation processing unit 523 of tube sheet;
Caulk weld Size calculation processing unit 524, design and build rule request for the weldering larynx size after being clashed into by foreign matter by described caulk weld and presurized water reactor nuclear islands equipment to compare, determine automatic surfacing layer welds larynx size and be less than or equal to that the caulk weld of the 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is less than or equal to the 4th preset value be the 5th affected area, and determine automatic surfacing layer welds larynx size and be greater than that the caulk weld of described 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is greater than described 4th preset value be the 6th affected area,
Caulk weld stress corrosion calculation processing unit 525, for obtaining and the chromium constituent content of the affected area of described caulk weld and described second preset value being compared, determine that the chromium constituent content of the affected area of the caulk weld on automatic surfacing layer is greater than described second preset value, and the affected area surface of caulk weld on automatic surfacing layer is tensile stress state, and determine that the chromium constituent content of affected area of the caulk weld on manual build up welding layer is less than described second preset value, and the affected area surface of caulk weld on manual build up welding layer is tensile stress state;
The in-service feasibility calculation processing unit 526 of caulk weld, for described caulk weld spout diameter and the 5th preset value being compared, determines that the caulk weld mouth of pipe that spout diameter is less than described 5th preset value is the 7th affected area.
Further, still please refer to Fig. 5 B, described injury repair module 53 comprises:
Unit 531 repaired by tube sheet, for carrying out polishing reparation to described first affected area, carries out REPAIR WELDING to described second affected area; Also for polishing to described 3rd affected area, to make the roughness on the affected area surface after polishing be less than or equal to the 6th preset value, and then the 3rd affected area surface after polishing is made to change into compressive stress state by tensile stress state; And for carrying out rounding off process to described 4th affected area, primary Ioops radioactive liquid residual on described tube sheet during to reduce In-service testing;
Caulk weld repairs unit 532, fills up metal for carrying out overhead welding reparation to described 5th affected area; Carry out polishing reparation to described 6th affected area, be less than or equal to described 6th preset value with the roughness on the caulk weld surface after making polishing reparation, the 6th affected area surface after repairing of guaranteeing to polish is compressive stress state; Also for polishing to described 7th affected area, to make described spout diameter be greater than described 5th preset value, and then enable eddy current probe through the described caulk weld mouth of pipe.
In specific implementation process, described reparation inspection module 54 specifically for:
Outward appearance detection, liquid penetration examination, size detection and ultrasound detection are carried out to the described tube sheet after repairing, outward appearance detection, liquid penetration examination, size detection and ray detection are carried out to the described caulk weld after repairing, stress test and the water pressure test are carried out to the described tube sheet after reparation and described caulk weld entirety, to guarantee that the described tube sheet after repairing and described caulk weld meet equipment code requirement.
Generally speaking, by implementing the application's scheme, efficiently solve existing SG field repair technology and cannot eliminate the technical problem of foreign object damage on the impact of SG equipment completely, can ensure that the caulk weld size after repairing meets the demands, and hardened layer and stress corrosion risk can be eliminated.
According to description above, above-mentioned nuclear power station steam generator tube sheet and caulk weld injury repair system are used for realizing above-mentioned nuclear power station steam generator tube sheet and caulk weld damage rehabilitation method, so, the embodiment of this system is identical with one or more embodiments of said method, has just repeated no longer one by one at this.
Those skilled in the art should understand, embodiments of the invention can be provided as method, system or computer program.Therefore, the present invention can adopt the form of complete hardware embodiment, completely software implementation or the embodiment in conjunction with software and hardware aspect.And the present invention can adopt in one or more form wherein including the upper computer program implemented of computer-usable storage medium (including but not limited to magnetic disc store, CD-ROM, optical memory etc.) of computer usable program code.
Although describe the preferred embodiments of the present invention, those skilled in the art once obtain the basic creative concept of cicada, then can make other change and amendment to these embodiments.So claims are intended to be interpreted as comprising preferred embodiment and falling into all changes and the amendment of the scope of the invention.
Obviously, those skilled in the art can carry out various change and modification to the present invention and not depart from the spirit and scope of the present invention.Like this, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technologies thereof, then the present invention is also intended to comprise these change and modification.
Claims (14)
1. a nuclear power station steam generator tube sheet and caulk weld damage rehabilitation method, described caulk weld is fixedly connected with tube sheet and the heat-transfer pipe of described steam generator, described damage is that foreign matter clashes into described tube sheet and described caulk weld forms, and it is characterized in that, described restorative procedure comprises step:
S1, foreign object damage inspection is carried out to described tube sheet and described caulk weld, to obtain damage check data;
S2, computing is carried out to described damage check data, to obtain the damage measurement process data of described tube sheet and described caulk weld;
S3, based on described damage measurement process data, injury repair is carried out to described tube sheet and described caulk weld;
S4, after described injury repair completes, to described tube sheet and described caulk weld carry out reparation inspection.
2. nuclear power station steam generator tube sheet as claimed in claim 1 and caulk weld damage rehabilitation method, it is characterized in that, described step S1 is specially:
Inspection obtains the pit depth described tube sheet being clashed into the affected area formed by foreign matter, and inspection obtain described caulk weld clashed into by foreign matter after weldering larynx size and caulk weld spout diameter.
3. nuclear power station steam generator tube sheet as claimed in claim 1 and caulk weld damage rehabilitation method, it is characterized in that, described step S2 is specially:
Based on described damage check data, Size calculation process, stress corrosion computing and the computing of In-service testing feasibility are carried out to described tube sheet and described caulk weld, to obtain damage measurement process data.
4. nuclear power station steam generator tube sheet as claimed in claim 1 and caulk weld damage rehabilitation method, it is characterized in that, described step S3 is specially:
Based on described damage measurement process data, described tube sheet and described caulk weld are welded and polish reparation.
5. nuclear power station steam generator tube sheet as claimed in claim 2 and caulk weld damage rehabilitation method, it is characterized in that, described step S2 specifically comprises:
The thickness that the pit depth of the affected area of described tube sheet and described tube sheet overlay cladding dispatched from the factory compares, the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is greater than the first preset value is the first affected area, and the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is less than or equal to described first preset value is the second affected area;
Obtain and the chromium constituent content of the affected area of described tube sheet and the second preset value are compared, determine that the affected area that chromium constituent content is less than the described tube sheet of described second preset value is the 3rd affected area, the surface of described 3rd affected area is tensile stress state;
Detect on described tube sheet overlay cladding and there is part that is sharp-pointed or groove, and described part that is sharp-pointed or groove is defined as the 4th affected area;
Weldering larynx size after being clashed into by foreign matter by described caulk weld and presurized water reactor nuclear islands equipment design and build rule request and compare, determine automatic surfacing layer welds larynx size and be less than or equal to that the caulk weld of the 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is less than or equal to the 4th preset value be the 5th affected area, and determine automatic surfacing layer welds larynx size and be greater than that the caulk weld of described 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is greater than described 4th preset value be the 6th affected area;
Obtain and the chromium constituent content of the affected area of described caulk weld and described second preset value are compared, determine that the chromium constituent content of the affected area of the caulk weld on automatic surfacing layer is greater than described second preset value, and the affected area surface of caulk weld on automatic surfacing layer is tensile stress state, and determine that the chromium constituent content of affected area of the caulk weld on manual build up welding layer is less than described second preset value, and the affected area surface of caulk weld on manual build up welding layer is tensile stress state;
Described caulk weld spout diameter and the 5th preset value are compared, determines that the caulk weld mouth of pipe that spout diameter is less than described 5th preset value is the 7th affected area.
6. nuclear power station steam generator tube sheet as claimed in claim 5 and caulk weld damage rehabilitation method, it is characterized in that, described step S3 specifically comprises:
Polishing reparation is carried out to described first affected area, REPAIR WELDING is carried out to described second affected area;
Described 3rd affected area is polished, to make the roughness on the affected area surface after polishing be less than or equal to the 6th preset value, and then makes the 3rd affected area surface after polishing change into compressive stress state by tensile stress state;
Rounding off process is carried out to described 4th affected area, primary Ioops radioactive liquid residual on described tube sheet during to reduce In-service testing;
Overhead welding reparation is carried out to described 5th affected area and fills up metal; Carry out polishing reparation to described 6th affected area, be less than or equal to described 6th preset value with the roughness on the caulk weld surface after making polishing reparation, the 6th affected area surface after repairing of guaranteeing to polish is compressive stress state;
Described 7th affected area is polished, to make described spout diameter be greater than described 5th preset value, and then enables eddy current probe through the described caulk weld mouth of pipe.
7. nuclear power station steam generator tube sheet as claimed in claim 1 and caulk weld damage rehabilitation method, it is characterized in that, described step S4 is specially:
Outward appearance detection, liquid penetration examination, size detection and ultrasound detection are carried out to the described tube sheet after repairing, outward appearance detection, liquid penetration examination, size detection and ray detection are carried out to the described caulk weld after repairing, stress test and the water pressure test are carried out to the described tube sheet after reparation and described caulk weld entirety.
8. a nuclear power station steam generator tube sheet and caulk weld injury repair system, described caulk weld is fixedly connected with tube sheet and the heat-transfer pipe of described steam generator, described damage is that foreign matter clashes into described tube sheet and described caulk weld forms, and it is characterized in that, described repair system comprises:
Damage inspection module, for carrying out foreign object damage inspection to described tube sheet and described caulk weld, to obtain damage check data;
Damage measurement processing module, for carrying out computing to described damage check data, to obtain the damage measurement process data of described tube sheet and described caulk weld;
Injury repair module, for carrying out injury repair based on described damage measurement process data to described tube sheet and described caulk weld;
Repair inspection module, for after described injury repair completes, reparation inspection is carried out to described tube sheet and described caulk weld.
9. nuclear power station steam generator tube sheet as claimed in claim 8 and caulk weld injury repair system, is characterized in that, described damage inspection module specifically for:
Inspection obtains the pit depth described tube sheet being clashed into the affected area formed by foreign matter, and inspection obtain described caulk weld clashed into by foreign matter after weldering larynx size and caulk weld spout diameter.
10. nuclear power station steam generator tube sheet as claimed in claim 8 and caulk weld injury repair system, is characterized in that, described damage measurement processing module specifically for:
Based on described damage check data, Size calculation process, stress corrosion computing and the computing of In-service testing feasibility are carried out to described tube sheet and described caulk weld, to obtain damage measurement process data.
11. nuclear power station steam generator tube sheet as claimed in claim 8 and caulk weld injury repair systems, is characterized in that, described injury repair module specifically for:
Based on described damage measurement process data, described tube sheet and described caulk weld are welded and polish reparation.
12. nuclear power station steam generator tube sheet as claimed in claim 9 and caulk weld injury repair systems, it is characterized in that, described damage measurement processing module comprises:
Tubesheet dimension calculation processing unit, compare for the pit depth of the affected area by described tube sheet and the described tube sheet overlay cladding thickness that dispatches from the factory, the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is greater than the first preset value is the first affected area, and the affected area determined to dispatch from the factory pit depth and described overlay cladding the difference of thickness is less than or equal to described first preset value is the second affected area;
Tube sheet stress corrosion calculation processing unit, for obtaining and the chromium constituent content of the affected area of described tube sheet and the second preset value being compared, determine that the affected area that chromium constituent content is less than the described tube sheet of described second preset value is the 3rd affected area, the surface of described 3rd affected area is tensile stress state;
, there is part that is sharp-pointed or groove for detecting on described tube sheet overlay cladding, and described part that is sharp-pointed or groove be defined as the 4th affected area in the in-service feasibility calculation processing unit of tube sheet;
Caulk weld Size calculation processing unit, design and build rule request for the weldering larynx size after being clashed into by foreign matter by described caulk weld and presurized water reactor nuclear islands equipment to compare, determine automatic surfacing layer welds larynx size and be less than or equal to that the caulk weld of the 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is less than or equal to the 4th preset value be the 5th affected area, and determine automatic surfacing layer welds larynx size and be greater than that the caulk weld of described 3rd preset value and manual build up welding layer to weld the caulk weld that larynx size is greater than described 4th preset value be the 6th affected area,
Caulk weld stress corrosion calculation processing unit, for obtaining and the chromium constituent content of the affected area of described caulk weld and described second preset value being compared, determine that the chromium constituent content of the affected area of the caulk weld on automatic surfacing layer is greater than described second preset value, and the affected area surface of caulk weld on automatic surfacing layer is tensile stress state, and determine that the chromium constituent content of affected area of the caulk weld on manual build up welding layer is less than described second preset value, and the affected area surface of caulk weld on manual build up welding layer is tensile stress state;
The in-service feasibility calculation processing unit of caulk weld, for described caulk weld spout diameter and the 5th preset value being compared, determines that the caulk weld mouth of pipe that spout diameter is less than described 5th preset value is the 7th affected area.
13. nuclear power station steam generator tube sheet as claimed in claim 12 and caulk weld injury repair systems, it is characterized in that, described injury repair module comprises:
Unit repaired by tube sheet, for carrying out polishing reparation to described first affected area, carries out REPAIR WELDING to described second affected area; Also for polishing to described 3rd affected area, to make the roughness on the affected area surface after polishing be less than or equal to the 6th preset value, and then the 3rd affected area surface after polishing is made to change into compressive stress state by tensile stress state; And for carrying out rounding off process to described 4th affected area, primary Ioops radioactive liquid residual on described tube sheet during to reduce In-service testing;
Caulk weld repairs unit, fills up metal for carrying out overhead welding reparation to described 5th affected area; Carry out polishing reparation to described 6th affected area, be less than or equal to described 6th preset value with the roughness on the caulk weld surface after making polishing reparation, the 6th affected area surface after repairing of guaranteeing to polish is compressive stress state; Also for polishing to described 7th affected area, to make described spout diameter be greater than described 5th preset value, and then enable eddy current probe through the described caulk weld mouth of pipe.
14. nuclear power station steam generator tube sheet as claimed in claim 8 and caulk weld injury repair systems, is characterized in that, described reparation inspection module specifically for:
Outward appearance detection, liquid penetration examination, size detection and ultrasound detection are carried out to the described tube sheet after repairing, outward appearance detection, liquid penetration examination, size detection and ray detection are carried out to the described caulk weld after repairing, stress test and the water pressure test are carried out to the described tube sheet after reparation and described caulk weld entirety.
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