CN103773942B - Thermal treatment device of field joint of steel containment of nuclear power plant and thermal treatment method - Google Patents
Thermal treatment device of field joint of steel containment of nuclear power plant and thermal treatment method Download PDFInfo
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Abstract
The invention relates to a thermal treatment device of a field joint of a steel containment of a nuclear power plant and a thermal treatment method, belonging to the technical field of construction of the nuclear power plant. The device mainly consists of a main framework (Z-1), heating insulators (Z-2), a traveling mechanism (Z-3), a temperature sensing apparatus (Z-4) and an automatic temperature controller (Z-5). During thermal treatment, the traveling mechanism of the thermal treatment device is supported at the upper edge of a wall plate of the containment and is moved along the upper edge, so that the heating insulators on both sides of the wall plate of the containment are located in a position for clamping the to-be-thermally-treated joint. Then, the temperature sensor is installed at the to-be-thermally-treated joint. After an electric heating apparatus is connected, under the closed loop control of the automatic temperature controller, the joint is heated to a predetermined temperature. According to the invention, the insulating cotton, the electric heating apparatus and the joint are compactly attached, and the joint quality is remarkably improved and the welding period is remarkably shortened by guaranteeing the thermal treatment quality and efficiency.
Description
Technical field
The present invention relates to a kind of device of steel containment vessel of nuclear power station erecting and welding, especially a kind of steel containment vessel of nuclear power station site weld thermal treatment unit, provides corresponding heat treating method simultaneously, belongs to Nuclear Power Station technical field.
Background technology
Reactor housing (CV), as the important component part of passive system, can effectively stop reactor housing internal pressure exceed design load and prevent radioactive substance from leaking under accident conditions, is one of visual plant ensureing that Nuclear Safety runs.AP1000 three generations steel containment vessel of nuclear power station is a stopping property steel container, comprise bottom (head), cylindrical shell and cover head three part, form by the high tough SA738Gr.B steel plate butt welding of 40mm ~ 50mm thick low-alloy, weld seam overall length is about 3400m, groove section is large, compare the heap-type Nuclear power plants such as CPR1000, EPR, welding job amount at least adds 8 times.
Nuclear power is built the specification of quality of all weld seams of CV very strict, and the compactness, obdurability, welding deformation amount etc. of welding joint are the quality index that must control and ensure.Particularly, for preventing the welding crack of the high tough SA738Gr.B steel plate of 40mm ~ 50mm thick low-alloy, the unrelieved stress eliminating postwelding existence guarantees welding joint comprehensive mechanical performance, the all weld seams of CV all need to take strict, accurate thermal treatment process, mainly comprise weld preheating, the thermal treatment of postwelding stress-removal etc.
In the construction of all AP1000 nuclear power generating sets of current China, thermal treatment work adopts flame baking method or simple support electrical heating method usually, there is following problem:
1. flame baking method is the heating of cyclicity concentration of local, under the objective condition that area of dissipation is large, the thermal treatment adopting this method to carry out weld seam cannot realize welding bead length, being uniformly distributed and constantization of thickness direction thermal treatment temp, thermal treatment quality can not be guaranteed, and the time being baked to specified temperature needs is long, the inflammable gas of consumption is many.
2. simple support electrical heating method is that repeatability supports fixing heat block in welded joints and lay insulating cotton on heat block, heat block and weld seam, insulating cotton and heat block can not fit tightly, thermal conduction and heat insulation effect poor, there is greater risk in thermal treatment quality, operating efficiency is low.
Summary of the invention
The technical problem to be solved in the present invention is: for above-mentioned existing heat treatment technics Problems existing, propose a kind of steel containment vessel of nuclear power station site weld thermal treatment unit contributing to improving welding efficiency, ensure to stablize welding quality, provide the steel containment vessel of nuclear power station site weld heat treating method by this device simultaneously.
In order to reach above object, basic technical scheme of the present invention is:
Steel containment vessel of nuclear power station site weld thermal treatment unit is primarily of main body framework (Z-1), heating warmer (Z-2), travel mechanism (Z-3), temperature sensor (Z-4), automatic temperature-controlled instrument (Z-5) composition;
Described main body framework (Z-1) is primarily of at least two root posts (1-11,1-12) on top band web plate (1-10), between the upper and lower every being fixed on the crossbeam between two root posts (1-21,1-22,1-23,1-24) formation;
Described heating warmer (Z-2) is formed primarily of electric heating device (2-R) and insulating cotton (2-W); The one side of described insulating cotton (2-W) has groove, and described electric heating device (2-R) is placed in groove and fits tightly, and wraps integrally with wire cloth (2-S);
Described travel mechanism (Z-3) by connect panel (3-1), from connect panel lower surface two couple towards downward-extension walk limiting plate (3-2), be installed on force transmission shaft (3-4) between relative walking limiting plate top, and the walking roller (3-3) be enclosed within force transmission shaft is formed;
Connection panel (3-1) the lower surface both sides of described travel mechanism (Z-3) fix a main body framework (Z-1) respectively, and the apparent surface of described main body framework installs a heating warmer (Z-2) respectively;
The signal output part of described temperature sensor (Z-4) connects the corresponding ports of automatic temperature control instrument (Z-5), the control output end of described automatic temperature control instrument connects electric heating device, in order to control the break-make of electric heating device according to the comparative result of temperature sensor input temperature values and default temperature control value.
Steel containment vessel of nuclear power station site weld heat treating method by apparatus of the present invention comprises the following steps:
The first step, the walking roller of described thermal treatment unit travel mechanism is supported on the upper edge of reactor housing wallboard, makes two main body framework being fixed with heating warmer respectively lay respectively at reactor housing wallboard surfaces externally and internally;
Second step, temperature sensor is placed in vertical commissure to be heated;
Along being movably walking mechanism on 3rd step, reactor housing wallboard annularly, the heating warmer on reactor housing wallboard two sides is made to be in the position clamping vertical weld seam to be heated;
4th step, connection electric heating device, under the closed-loop control of automatic temperature-controlled instrument, be heated to preset temperature by vertical weld seam.
Above-mentioned steps as the preheat process before being applied to welding, is then removed thermal treatment unit after the 4th step and is positioned at surface to be welded back portion, weld; As the destressing thermal treatment after being applied to welding, then after the 4th step, thermal treatment unit is moved to next commissure.
It is that the apparent surface of described main body framework installs a heating warmer (Z-2) respectively, and between main body framework and thermal insulation device, assign movable force transmitting board (B-1, B-2, B-3) that thermal treatment unit of the present invention further improves; Be provided with the vertical reinforced tube (1-31,1-32,1-33) be fixedly connected with crossbeam (1-21,1-22,1-23,1-24) between described two root posts (1-11,1-12), described reinforced tube be intervally distributed with the clamping screw (G) that movable force transmitting board is withstood in the inner.
Heat treating method of the present invention improves accordingly further, in described second step, also be included in the jig that vertical weld seam both sides fixedly catch on main body framework crossbeam two ends respectively, after the heating warmer on wallboard two sides is in the position clamping vertical weld seam to be heated, tightening clamping screw, by holding out against activity power transmission steel plate, heating warmer and reactor housing wallboard more being fitted tightly.
Adopt device of the present invention to carry out the thermal treatment of steel containment vessel of nuclear power station site weld, relative to existing flame baking method or simple support electrical heating method, there is following remarkable advantage:
1. thennal conduction enhancement and heat insulation effect, ensure the homogeneous temperature of whole piece welding bead length, width, thickness direction and constant, thermal treatment quality can effectively improve;
2. apparatus structure is simple, easy for installation, can along the circumferential direction quick travel is to any weld seam to be heated, and thermal treatment construction efficiency improves greatly, and the production cycle of steel containment vessel of nuclear power station also shortens relatively.
Accompanying drawing explanation
Below in conjunction with accompanying drawing, the present invention is further illustrated.
Fig. 1 is steel containment vessel of nuclear power station one-piece construction schematic diagram.
Fig. 2 is the thermal treatment unit structural representation of one embodiment of the invention.
Fig. 3 is the main body framework perspective view in Fig. 2 embodiment.
Fig. 4 is spill jig in Fig. 2 embodiment and Wedge device perspective view.
Fig. 5 is the heating warmer structural representation in Fig. 2 embodiment.
Fig. 6 is the activity power transmission steel plate position structural representation in Fig. 2 embodiment.
Fig. 6-1 is the B-B cross-sectional view of Fig. 6.
Fig. 7 is the travel mechanism perspective view in Fig. 2 embodiment.
Fig. 7-1 is the side-view of Fig. 7.
Fig. 8 is that briquette structure schematic diagram is fixed in the thermopair working end in Fig. 2 embodiment.
Fig. 8-1 is the side-view of Fig. 8.
Fig. 9 is steel containment vessel of nuclear power station welded construction schematic diagram.
Fig. 9-1 is the using state structural representation of Fig. 2 embodiment.
Embodiment
Referring to accompanying drawing, the preferred embodiments of the present invention are described.
As shown in Figure 1, the steel containment vessel of nuclear power station (CV) of the present embodiment comprises segment-shaped bottom (head), round tube type cylindrical shell and segment-shaped cover head three part, and diameter is 39.6m.Wherein, bottom (head) and cover head form by totally 64 pieces of high tough SA738Gr.B steel plate butt weldings of hyperboloid.Cylindrical shell is made up of 11 circle wallboards, often encloses and is formed by the high tough SA738Gr.B steel plate butt welding of 12 pieces of single curved surfaces, comprise 132 vertical weld seams (also known as longitudinal joint) and 12 circumferential welds.Need to carry out thermal pretreatment before all weld seam welderings, part weld seam postwelding need carry out stress-removal thermal treatment.
The weld preheating process of the steel containment vessel of nuclear power station site weld of the present embodiment adopts the thermal treatment unit shown in Fig. 2, comprises main body framework Z-1, heating warmer Z-2, travel mechanism Z-3, thermopair Z-4, automatic temperature-controlled instrument Z-5.Temperature sensor adopts thermopair Z-4, its signal output part meets automatic temperature control instrument Z-5(model WCK-240, the southeast, Wujiang welding and cutting device company limited manufacture) corresponding ports, the control output end of automatic temperature control instrument Z-5 connects electric heating device, by the parameter preset, heat treatment process is carried out controlling and adjusted, in order to control the break-make of electric heating device according to the comparative result of temperature sensor input temperature values and default temperature control value.
Main body framework Z-1 concrete structure as shown in Figure 3, the left and right border of main body framework Z-1 is symmetrical corniform upright column 1-11, the 1-12 of two of top band web plate 1-10, and its outside surface is upper and lower along its length is equidistantly welded with four equal length square tube beam 1-21,1-22,1-23,1-24.
Be provided with between two root post 1-11,1-12 and weld first, second and third that be connected with crossbeam 1-21,1-22,1-23,1-24 and arrange the vertical square tube 1-31 that puts more energy into, 1-32,1-33; The secondary series square tube 1-32 that puts more energy into is welded in the mid point of crossbeam, and all the other two row 1-31,1-33 are with secondary series 1-32 for symmetry centre is symmetrical, and all square tubes of putting more energy into all are intervally distributed with the clamping screw G that movable force transmitting board (see Fig. 6) is withstood in the inner.
For the ease of settling, the present embodiment has made the opening up spill jig K shown in a picture group 4, is weldingly fixed on vertical weld seam both sides during use, to catch on the two ends of each crossbeam respectively, and by wedge X wedging.
Heating warmer Z-2 as shown in Figure 5, comprise the electric heating block 2-R(track type ceramic electrical heating block as electric heating device, honest Electrical Appliances Co., Ltd manufactures) and insulating cotton 2-W, the one side of insulating cotton 2-W is groove-like, thickness leaves compression surplus, and its recess width and the degree of depth and electric heating block 2-R match, and electric heating block 2-R just puts and is dissolved in the groove of insulating cotton 2-W, after fitting tightly, wrap integrally with Stainless Steel Cloth 2-S.
As shown in Fig. 6 and Fig. 6-1, the put more energy into contact surface of square tube and heating warmer of three row of main body framework Z-1 is respectively equipped with activity power transmission steel plate B-1, B-2, B-3 that three pieces of compacted screw rod G withstand.
Travel mechanism Z-3 is as shown in Fig. 7 and Fig. 7-1, comprise and connect panel 3-1, two to from connecting walking limiting plate 3-2, walking roller 3-3, the force transmission shaft 3-4 of panel lower surface towards downward-extension, force transmission shaft 3-4 is installed between relative walking limiting plate top, and walking roller 3-3 is enclosed within force transmission shaft.The connection panel 3-1 lower surface both sides of this travel mechanism Z-3 fix a main body framework Z-1 respectively, and the apparent surface of main body framework installs a heating warmer Z-2 respectively.
The conveniently arrangement of thermopair, the present embodiment has made the fluting shown in Fig. 8 and Fig. 8-1 and has fixed briquetting 4-10, is welded on vertical weld seam side during use, is inserted wherein the working end of thermopair Z-4.
The steel containment vessel of nuclear power station welded construction of the present embodiment as shown in Figure 9, is first welded all vertical weld seam of bottom N girth sheets, then is welded all vertical weld seam ZF-1---the ZF-12 of N+1 girth sheets, carry out the welding of circumferential weld HF between two circles afterwards.Carry out the welding of vertical weld seam forward and backward, need butt welded seam to carry out thermal pretreatment and destressing thermal treatment respectively.Heat treated step following (see Fig. 9-1):
The first step, the walking roller 3-3 of thermal treatment unit travel mechanism Z-3 is supported on the upper edge of reactor housing wallboard Z, makes the two main body framework Z-1 being fixed with heating warmer Z-2 respectively lay respectively at reactor housing wallboard Z surfaces externally and internally;
Second step, by three pieces slot fixing briquetting 4-10 between the upper and lower every upper, middle and lower three place being welded on vertical weld seam side, respectively the working end of three thermopair Z-4 is assigned into respectively in the groove of each fixing briquetting 4-10;
Along being movably walking mechanism Z-3 on 3rd step, reactor housing wallboard Z annularly, the heating warmer Z-2 on reactor housing wallboard Z two sides is made to be in the position clamping vertical weld seam ZF-1 to be heated; The opening up spill jig K catching on main body framework Z-1 each crossbeam two ends is welded and fixed respectively in these vertical weld seam both sides, and by each crossbeam of wedge X wedging; Tightening again and compress all screw rod G, by holding out against each activity power transmission steel plate, heating warmer Z-2 and reactor housing wallboard being fitted tightly;
4th step, manipulate automatic temperature-controlled instrument Z-5, connect heating warmer Z-2 electricity heating block, under the closed-loop control of automatic temperature-controlled instrument, vertical weld seam is heated to preset temperature.
For the thermal pretreatment before welding (automatic welding or manually weldering), the preheating temperature setting automatic temperature-controlled instrument is 100 ~ 200 DEG C, and heating rate is 200 ± 20 DEG C/h; For the stress-removal thermal treatment after welding, the holding temperature setting automatic temperature-controlled instrument is 595 ~ 615 DEG C, and soaking time is 2 ± 0.1 hours; Time more than 425 DEG C, 56 DEG C/h≤rate temperature change (heating or rate of cooling)≤110 DEG C/h.
Afterwards, unclamp wedge X, thermal treatment unit is moved to other weld seams by walking roller by steel containment vessel wallboard circumferential direction annularly, carries out weld seam ZF-2, ZF-3, ZF-4 successively with reference to above step ... the thermal treatment of ZF-12.
Facts have proved, the steel containment vessel of nuclear power station site weld thermal treatment unit of the present embodiment and heat treating method is adopted to make to fit tightly between insulating cotton, electric heating device, weld seam, by guaranteeing thermal treatment quality and efficiency, significantly improving weldquality, shortening the welding duration.
It should be noted that, above-described embodiment is nonrestrictive, and many structures such as the geometric shape of thermal treatment unit can carry out adaptability revision according to the profile feature of workpiece to be heated.
Claims (8)
1. a steel containment vessel of nuclear power station site weld thermal treatment unit, is characterized in that: primarily of main body framework (Z-1), heating warmer (Z-2), travel mechanism (Z-3), temperature sensor (Z-4), automatic temperature-controlled instrument (Z-5) composition;
Described main body framework (Z-1) is primarily of at least two root posts (1-11,1-12) on top band web plate (1-10), between the upper and lower every being fixed on the crossbeam between two root posts (1-21,1-22,1-23,1-24) formation;
Described heating warmer (Z-2) is formed primarily of electric heating device (2-R) and insulating cotton (2-W); The one side of described insulating cotton (2-W) has groove, and described electric heating device (2-R) is placed in groove and fits tightly, and wraps integrally with wire cloth (2-S);
Described travel mechanism (Z-3) by connect panel (3-1), from connect panel lower surface two couple towards downward-extension walk limiting plate (3-2), be installed on force transmission shaft (3-4) between relative walking limiting plate top, and the walking roller (3-3) be enclosed within force transmission shaft is formed;
Connection panel (3-1) the lower surface both sides of described travel mechanism (Z-3) fix a main body framework (Z-1) respectively, and the apparent surface of described main body framework installs a heating warmer (Z-2) respectively;
The signal output part of described temperature sensor (Z-4) connects the corresponding ports of automatic temperature control instrument (Z-5), the control output end of described automatic temperature control instrument connects electric heating device, in order to control the break-make of electric heating device according to the comparative result of temperature sensor input temperature values and default temperature control value.
2. steel containment vessel of nuclear power station site weld thermal treatment unit according to claim 1, it is characterized in that: the apparent surface of described main body framework installs a heating warmer (Z-2) respectively, and between main body framework and heating warmer, assign movable force transmitting board (B-1, B-2, B-3); Be provided with the vertical reinforced tube (1-31,1-32,1-33) be fixedly connected with crossbeam (1-21,1-22,1-23,1-24) between described two root posts (1-11,1-12), described reinforced tube be intervally distributed with the clamping screw (G) that movable force transmitting board is withstood in the inner.
3. adopt the heat treating method of steel containment vessel of nuclear power station site weld thermal treatment unit described in claim 1, it is characterized in that comprising the following steps:
The first step, the walking roller of described thermal treatment unit travel mechanism is supported on the upper edge of reactor housing wallboard, makes two main body framework being fixed with heating warmer respectively lay respectively at reactor housing wallboard surfaces externally and internally;
Second step, temperature sensor is placed in vertical commissure to be heated;
3rd step, be movably walking along the upper edge of reactor housing wallboard mechanism, makes the heating warmer on reactor housing wallboard two sides be in the position clamping vertical weld seam to be heated;
4th step, connection electric heating device, under the closed-loop control of automatic temperature-controlled instrument, be heated to preset temperature by vertical weld seam.
4. adopt the heat treating method of steel containment vessel of nuclear power station site weld thermal treatment unit described in claim 2, it is characterized in that comprising the following steps:
The first step, the walking roller of described thermal treatment unit travel mechanism is supported on the upper edge of reactor housing wallboard, makes two main body framework being fixed with heating warmer respectively lay respectively at reactor housing wallboard surfaces externally and internally;
Second step, temperature sensor is placed in vertical commissure to be heated;
Along being movably walking mechanism on 3rd step, reactor housing wallboard annularly, the heating warmer on reactor housing wallboard two sides is made to be in the position clamping vertical weld seam to be heated; Fixedly catching on the jig at main body framework crossbeam two ends in vertical weld seam both sides respectively, tighten clamping screw, by holding out against activity power transmission steel plate, heating warmer and reactor housing wallboard being fitted tightly;
4th step, connection electric heating device, under the closed-loop control of automatic temperature-controlled instrument, be heated to preset temperature by vertical weld seam.
5. the heat treating method of steel containment vessel of nuclear power station site weld thermal treatment unit according to claim 4, it is characterized in that: described jig is opening up spill jig, in described second step, spill jig is weldingly fixed on vertical weld seam both sides respectively, catch on the two ends of each crossbeam, and by wedge wedging.
6. the heat treating method of steel containment vessel of nuclear power station site weld thermal treatment unit according to claim 4, it is characterized in that: described temperature sensor is thermopair, at the fixing briquetting of vertical weld seam side welding fluting in described 3rd step, the working end of thermopair is inserted in the groove of fixing briquetting.
7. the heat treating method of steel containment vessel of nuclear power station site weld thermal treatment unit according to claim 5 or 6, it is characterized in that: described thermal treatment is the thermal pretreatment before welding, the preheating temperature of described automatic temperature-controlled instrument setting is 100 ~ 200 DEG C, and heating rate is 200 ± 20 DEG C/h.
8. the heat treating method of steel containment vessel of nuclear power station site weld thermal treatment unit according to claim 5 or 6, it is characterized in that: described thermal treatment is the stress-removal thermal treatment after welding, the holding temperature of described automatic temperature-controlled instrument setting is 595 ~ 615 DEG C, soaking time is 2 ± 0.1 hours, and time more than 425 DEG C, 56 DEG C/h≤rate temperature change≤110 DEG C/h.
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| CN1614040A (en) * | 2003-11-06 | 2005-05-11 | 中国科学院力学研究所 | Material thermal treating surface temperature realtime monitoring system |
| CN102102455A (en) * | 2010-12-22 | 2011-06-22 | 中国石油天然气集团公司 | Heat treatment construction method of large storage tank wallboard |
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