KR101711367B1 - A Nuclear Steam Generator Circular Seam Heat Treatment Unit System and the Purpose thereof - Google Patents

Abstract

The present invention discloses a nuclear steam generator annular weld heat treatment unit system and its use, which system comprises a heat treatment equipment; Flow control device capable of flow control; Temperature and flow controllable open ventilation; A displacement measurement system for measuring the edge displacement of the steam generator support plate; Temperature measurement system; And non-destructive testing equipment for detecting, comparing and analyzing the eddy currents of at least 20 heat exchange tubes around the support plate before and after the heat treatment to ascertain whether the heat exchange tubes have pits. The nuclear steam generator annular weld heat treatment unit system can be used in a nuclear steam generator manufacturing process that docks the upper annular welded joint and then docks the lower annular welded joint to prevent pitting by permanent indentations on the heat exchange tubes But the steam generator manufacturing process is optimized to greatly shorten the manufacturing cycle of the entire steam generator.

Description

TECHNICAL FIELD [0001] The present invention relates to a nuclear steam generator annular welded joint heat treatment unit system,

The present invention relates to a nuclear heat treatment technique, and more particularly, to a control technique for preventing a pit of a heat exchange tube during an annular weld heat treatment process of a nuclear steam generator, and more particularly, to a nuclear steam generator annular weld heat treatment unit system and Lt; / RTI >

1, the nuclear steam generator includes an upper component 10 and a lower component 20, which has an upper annular welded joint 11, and the lower component 20 ) Has a corresponding lower annular welded joint (21). During the manufacturing process of the nuclear steam generator, the upper annular weld joint 11 and the lower annular weld joint 21 must be subjected to a local heat treatment.

Nuclear steam generators have high design requirements and complex manufacturing processes, and local heat treatment processes of annular welded joints, which play an important role, have specific technical requirements. Due to the large size and complex structure of the steam generator, it is necessary not only to eliminate the welding residual stress during heat treatment but also to prevent the permanent indentation on the heat exchange tubes due to the uneven thermal expansion of the parts during heat treatment. Should be. Thus, an effective control technique is utilized to prevent the pits of the heat exchange tubes during the annular welded joint local heat treatment process.

On the other hand, control techniques to prevent pits in the heat exchange tubes can prevent pits in the heat exchange tubes due to permanent indentations during the heat exchange tube heat treatment process; On the other hand, the successful application of this technique can optimize the manufacturing process of the steam generator, thus greatly shortening the manufacturing cycle of the entire steam generator. Two patterns can be used in the manufacturing sequence for the last two annular weld joints during the steam generator manufacturing process. Pattern 1: dock the upper annular welded joint (11) and then the lower annular welded joint (21). Pattern 2: dock the lower annular weld joint 21 and then the upper annular weld joint 11. In the prior art, the manufacturing sequence of the steam generators of the domestic and foreign similar manufacturers, that is, the steam generator manufacturing procedure, is performed by first docking the lower annular weld joint 21 and then docking the upper annular weld joint 11 . However, the upper component is mostly a structural component, which is made of carbon steel or stainless steel as the main material, is simple to manufacture, can be purchased externally, has a short manufacturing cycle and has welding conditions of a priority assembly; The lower end enclosure of the lower component has a complicated structure, various manufacturing processes, considerable welding and machining effort and a long manufacturing cycle. If the manufacturing sequence of Pattern 1 can be applied, the manufacturing cycle of the entire steam generator can be shortened by about six months. Pattern 1, however, will increase the risk of pit formation in the heat exchange tubes and greatly increase control difficulties.

Thus, for pattern 1 (a steam generator manufacturing process in which the upper annular welded joint is docked and then the lower annular welded joint is docked), control techniques should be developed to effectively prevent the pit in the heat exchange tube.

The object of the present invention is to solve the above problems by providing an annular welded joint heat treatment technique for a steam generator for docking an upper annular welded joint and then docking a lower annular welded joint and thereby preventing a pit on the heat exchange tube .

As a specific means for achieving the above object, the present invention provides a nuclear steam generator annular weld heat treatment unit system, comprising: a heat treatment equipment; A flow rate controllable cool air vent connected to an open hole on the steam generator housing; A temperature and flow controllable hot air vent connected to an open hole on the steam generator housing; A displacement measurement system for measuring the edge displacement of the steam generator support plate; Temperature measurement system; And nondestructive testing equipment for detecting, comparing and analyzing the eddy currents of at least twenty heat exchange tubes around the support plate before and after the heat treatment to ascertain whether the heat exchange tubes have pits.

In the nuclear steam generator annular welded joint heat treatment unit system, the heat treatment equipment includes an electric heating plate, a thermal insulation material, a plurality of thermocouples and an electric heating numerical control (CNC) system.

In addition, the heat treatment apparatus further includes an electric hot plate fixing device and a heat insulating material fixing device.

In the nuclear steam generator annular weld heat treatment unit system, the flow rate controllable cold air vent includes cooling equipment, ventilation ducts, flow control cabinets, and flow meters.

In the nuclear steam generator annular weld heat treatment unit system, the maximum air flow rate of the cooling equipment is at least 10000 m3 / h and the flow rate can be steplessly adjusted during use.

In the nuclear steam generator annular weld heat treatment unit system, the temperature and flow rate controllable hot air vents include heating equipment, ventilation ducts, flow control cabinets, temperature control cabinets, flow meters, and electric heaters.

In the nuclear steam generator annular weld heat treatment unit system, the maximum air flow rate of the heating equipment is at least 10000 m3 / h, and the flow rate can be adjusted unauthorized during use.

In the nuclear steam generator annular weld heat treatment unit system, the minimum electric power of the electric heater is 20 kW, and the maximum adjustable temperature is 250 캜.

In the nuclear steam generator annular weld heat treatment unit system, the maximum edge displacement of the support plate may not exceed 1.5 ° at an angle.

In the nuclear steam generator annular weld heat treatment unit system, the temperature measurement system includes a plurality of thermocouples that measure the temperature of the steam generator in different zones.

The present invention also provides use of the nuclear steam generator annular weld heat treatment unit system. The nuclear steam generator annular weld joint includes an upper annular weld joint and a lower annular weld joint which can be used in a nuclear steam generator manufacturing process to dock a top annular weld seam and then dock a bottom annular weld join.

The present invention as described above has the following effects.

The nuclear steam generator annular weld heat treatment unit system disclosed in the present invention can be used in a nuclear steam generator manufacturing process (this process first docks the upper annular weld seam and then docks the lower annular weld seam) The steam generator manufacturing process is optimized so as not only to prevent pits on the heat exchange tubes due to the permanent indentation caused by the support plate deformation due to thermal expansion, but also to greatly shorten the manufacturing cycle of the entire steam generator.

BRIEF DESCRIPTION OF THE DRAWINGS Figure 1 is a schematic view of a steam generator annular weld joint location in the prior art;
2 is a schematic view of the location of the cooling equipment connectors in the local heat treatment process of the upper annular welded joint 11 of the nuclear steam generator according to the invention.
3 is a cross-sectional view of U1 and U2 connectors in FIG.
4 is a schematic view of the heating and cooling equipment connector locations of the local heat treatment process of the lower annular weld joint 21 of the nuclear steam generator according to the present invention.

The objects, features and advantages of the present invention will become more apparent from the following detailed description. Hereinafter, a technique according to the present invention will be described in detail with reference to the accompanying drawings.

In order to prevent the heat exchange tubes from being pitched, the annular welded joint heat treatment process requires a complete heat treatment equipment, a flow controllable freeze vent, a set of temperature and flow controllable hot aeration, displacement measurement system, temperature measurement system and nondestructive inspection equipment .

The heat treatment equipment includes an electric heating plate, a thermal insulation material, a thermocouple, an electric heating numerical control system, an electric heating plate fixing device, and a heat insulation fixing device. The heat treatment equipment performs a heat treatment for the nuclear steam generator.

The flow rate controllable freezing ventilation system includes cooling equipment, ventilation ducts, flow control cabinets, and flow meters. During the heat treatment process the device is connected to an open hole on the steam generator housing to draw cool air or extract warmth. The maximum air flow rate of the cooling equipment is at least 10000 m 3 / h, and the flow rate can be adjusted unauthorized during the process.

The temperature and flow controllable hot air vents include heating equipment, ventilation ducts, flow control cabinets, temperature control cabinets, flow meters, and electric heaters. During the heat treatment process the device is connected to an open hole on the steam generator housing to draw warmth. The maximum air flow rate of the heating equipment is at least 10000 m < 3 > / h, and the flow rate can be adjusted unauthorized during the process. The minimum power of the electric heater is 20 kW, and the maximum adjustable temperature is 250 캜.

The displacement measurement system applies special measurement equipment to measure the edge displacement of the support plate for opening and closing the plurality of open holes formed in the housing of the nuclear steam generator. Measuring equipment collects, monitors and analyzes data through connected equipment. The four measuring devices are distributed on the edge of the supporting plate, two of them are distributed over two inspection holes on the steam generator, and two different measuring devices are distributed perpendicularly to the two measuring devices.

The temperature measurement system comprising a plurality of thermocouples; Different numbers of thermocouples during the heat treatment process are placed in the heat exchange tubes, in the hand holes and in the inspection holes, respectively, to measure the temperature in different zones, thus providing data for effective control of cold and warm capacity.

The nondestructive testing equipment is used to detect, compare and analyze the eddy currents of at least 20 heat exchange tubes around the steam generator support plate before and after the heat treatment to ascertain whether the heat exchange tubes have pits or whether the control technique is successful .

All of the above devices are installed prior to the annular weld joint thermal treatment. During the heat treatment process, as well as the cold / warm capacity and temperature, and the opening and closing of the openings on the steam generator housing are adjusted by the monitoring results of the support plate edge displacements and the temperature monitoring results of the thermocouples at different locations. It can be judged whether or not the control technique for preventing the pit on the heat exchange tube by the result of the eddy current test of the heat exchange tube is successful. During the heat treatment process, the maximum angle converted from the support plate edge displacement shall not exceed 1.5 ° during the control.

S1, S2, T1, T2, and T3 in a flow controllable cool air vent and a temperature and flow controllable hot air vents during a local heat treatment, T2, U1, U2, U3, U4 are shown in FIGS. 2 and 3, wherein U1 to U4 connectors are uniformly positioned in the circumference of the steam generator housing in a distribution schematic as shown in FIG. During the heat treatment process, the open / close states of specific connectors and connectors are shown in Table 1. In ten ways as shown in Table 1, any scheme can achieve a particular effect; Equipment A, B, and C are cooling equipment, which are connected to the corresponding connectors in Table 1.

Upper annular welded joints (11) Pitting prevention measures of heat exchange tubes measures Device connector Heating step Insulation stage Cooling step NOTE (In the table, the opening / closing of other connectors except the connectors of the connecting equipment) One A S1 Air extraction Air extraction Air extraction Open only U1 to U4, close other connectors 2
A S1 Air extraction Air extraction Air extraction Open only U1 to U4 and close other connectors B R1 Air extraction Air extraction Air extraction 3
A S1 Air extraction Air extraction Air extraction Other connectors close
C U1 ~ U4 Blowing air Blowing air Blowing air 4

A S1 Air extraction Air extraction Air extraction Other connectors close

B R1 Air extraction Air extraction Air extraction C U1 ~ U4 Blowing air Blowing air Blowing air 5
A S1 Air extraction Air extraction Air extraction Open only U1 to U4 and close other connectors B T1 Air extraction Air extraction Air extraction 6

A S1 Air extraction Air extraction Air extraction Other connectors close B T1 Air extraction Air extraction Air extraction C U1 ~ U4 Blowing air Blowing air Blowing air 7 A R1 Air extraction Air extraction Air extraction Open only U1 to U4 and close other connectors 8
A R1 Air extraction Air extraction Air extraction Other connectors close
C U1 ~ U4 Blowing air Blowing air Blowing air 9
A R1 Air extraction Air extraction Air extraction Open only U1 to U4 and close other connectors B T1 Air extraction Air extraction Air extraction 10

A R1 Air extraction Air extraction Air extraction Other connectors close
B T1 Air extraction Air extraction Air extraction C U1 ~ U4 Blowing air Blowing air Blowing air

S2, T1, T2, U1, < / RTI > < RTI ID = 0.0 > U1, < / RTI & U2, U3, U4) are shown in Figs. 3 and 4. Fig. During the heat treatment process, the open / close states of specific connectors and connectors are shown in Table 2. Any of the ten approaches as shown in Table 2 can achieve a particular effect; Equipment A, B1 and B2 are cooling equipment, and C is heating equipment. These equipment are connected to the corresponding connectors in Table 2.

Lower annular welded joints (21) Pitting prevention measures of heat exchange tubes measures Device connector Heating step Insulation stage Cooling step NOTE (In the table, the opening / closing of other connectors except the connectors of the connecting equipment) One
A S2 Chill blow Chill blow Chill blow Heating and insulation steps: other connectors except open connector R1 are closed
Cooling phase: Other connectors except the closed connector R1 are open B1 U1 Chill blow Chill blow / B2 S1 / / Chill blow C U2 Open Blow Open Blow Open Blow 2
A S1 Chill blow Chill blow Chill blow Heating and insulation steps: other connectors except open connector R1 are closed
Cooling phase: Other connectors except the closed connector R1 are open B1 U1 Chill blow Chill blow / B2 S2 / / Chill blow C U2 Open Blow Open Blow Open Blow 3
A S2 Chill blow Chill blow Chill blow Other connectors except for connector R1 opened at all steps are closed B1 U1 Chill blow Chill blow / C U2 Open Blow Open Blow Open Blow 4

A S1 Chill blow Chill blow Chill blow Other connectors except for connector R1 opened at all steps are closed B1 U1 Chill blow Chill blow / C U2 Open Blow Open Blow Open Blow 5
A S2 Chill blow Chill blow Chill blow Heating and insulation steps: other connectors except open connector R1 are closed
Cooling phase: Other connectors except the closed connector R1 are open B2 S1 / / Chill blow C U2 Open Blow Open Blow Open Blow 6

A S1 Chill blow Chill blow Chill blow Heating and insulation steps: other connectors except open connector R1 are closed
Cooling phase: Other connectors except the closed connector R1 are open B2 S2 / / Chill blow C U2 Open Blow Open Blow Open Blow 7
A S2 Chill blow Chill blow Chill blow Other connectors except for connector R1 opened at all steps are closed C U2 Open Blow Open Blow Open Blow 8
A S1 Chill blow Chill blow Chill blow Other connectors except for connector R1 opened at all steps are closed C U2 Open Blow Open Blow Open Blow 9
A S2 Chill blow Chill blow Chill blow Heating and insulation steps: other connectors except open connector R1 are closed
Cooling phase: Other connectors except the closed connector R1 are open B1 U1 Chill blow Chill blow / B2 S1 Chill blow Chill blow Chill blow C U2 Open Blow Open Blow Open Blow 10

A S1 Chill blow Chill blow Chill blow Heating and insulation steps: other connectors except open connector R1 are closed
Cooling phase: Other connectors except the closed connector R1 are open

Note: In Table 2, "/" indicates that the connector connecting the equipment is closed.

The nuclear steam generator annular weld heat treatment unit system provided in the present invention is used in the nuclear steam generator manufacturing process in which the upper annular welded joint is docked and the lower annular welded joint is docked, and the amount of use of the heating equipment and cooling equipment, By controlling the open / close operation time of the heat exchanger tube, the application parameters of the heating equipment and the cooling equipment, and the maximum limit of the support plate edge displacement, it is possible to prevent the pits on the heat exchange tube due to the permanent indentation caused by the support plate deformation due to non- Optimize the steam generator manufacturing process to significantly shorten the manufacturing cycle of the steam generator.

While the present invention has been described in detail with reference to the preferred embodiments described above, it should be understood that the above description is not limited to the present invention. It will be apparent that those skilled in the art will be able to variously modify and substitute the invention upon reading the foregoing description. Accordingly, the scope of protection of the present invention falls within the scope defined by the claims.

Claims (10)

A nuclear steam generator annular welded joint heat treating unit device,
Heat treatment equipment for heat treatment process of nuclear steam generator;
A flow rate controllable cool air vent for extracting cool air blown and warm air in the nuclear steam generator during the heat treatment process;
A temperature and flow rate controllable hot air blowing device for capturing warmth in the nuclear steam generator during the heat treatment process;
A displacement measurement system for measuring an edge displacement of the support plate for opening and closing the plurality of open holes formed in the housing of the nuclear steam generator;
A temperature measurement system for measuring the temperature in the nuclear steam generator during the heat treatment process to control the capacity of the cool air and the warm air; And
Comparing and analyzing the eddy currents of at least 20 heat exchange tubes around the support plate before and after the heat treatment process and judging whether the prevention of pits on the heat exchange tubes is successful by the result of the inspection of the eddy current, Lt; / RTI >
The maximum edge displacement of the support plate does not exceed 1.5 [deg.] By an angle,
The nuclear steam generator annular weld heat treatment unit device comprises:
The upper annular welded joint of the nuclear steam generator is docked, the lower annular welded joint is docked,
A nuclear steam generator annular weld joint heat treatment unit for adjusting the capacity and temperature of the cold and warm air and the opening and closing of the open holes by the monitoring result of the temperature of the thermocouples at a position different from the monitoring result of the edge displacement of the support plate during the heat treatment process . The method according to claim 1,
The heat treatment equipment includes an electric heating plate, a thermal insulation material, a plurality of thermocouples, and an electric heating numerical control (CNC) system. The method according to claim 1,
The flow controllable cold air vent has an atomic steam generator annular weld heat treatment unit device including a cooling device, a ventilation duct, a flow control cabinet, and a flow meter. The method of claim 3,
Wherein the maximum air flow rate of the cooling equipment is at least 10000 m3 / h and the flow rate is adjusted steplessly during use. The method according to claim 1,
Wherein the temperature and flow controllable hot air vents comprise a heating device, a vent duct, a flow control cabinet, a temperature control cabinet, a flow meter, and an electric heater. 6. The method of claim 5,
Wherein the maximum air flow rate of the heating equipment is at least 10000 m3 / h and the flow rate is steplessly adjusted during use. 6. The method of claim 5,
Wherein the minimum electric power of the electric heater is 20 kW and the maximum adjustable temperature is 250 캜. delete The method according to claim 1,
Wherein the temperature measurement system comprises a plurality of thermocouples that measure the temperature of the steam generator in different zones. delete

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