WO2016070301A1 - Heat treatment device system for circular seam of nuclear power steam generator and use thereof - Google Patents

Heat treatment device system for circular seam of nuclear power steam generator and use thereof Download PDF

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Publication number
WO2016070301A1
WO2016070301A1 PCT/CN2014/001169 CN2014001169W WO2016070301A1 WO 2016070301 A1 WO2016070301 A1 WO 2016070301A1 CN 2014001169 W CN2014001169 W CN 2014001169W WO 2016070301 A1 WO2016070301 A1 WO 2016070301A1
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Prior art keywords
steam generator
heat treatment
treatment device
flow
device system
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PCT/CN2014/001169
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French (fr)
Chinese (zh)
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李双燕
徐超
张茂龙
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上海电气核电设备有限公司
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Priority to KR1020157034460A priority Critical patent/KR101711367B1/en
Priority to GB1519229.7A priority patent/GB2529576B/en
Priority to ROA201700120A priority patent/RO132254B1/en
Priority to ZA2015/08039A priority patent/ZA201508039B/en
Publication of WO2016070301A1 publication Critical patent/WO2016070301A1/en

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    • C—CHEMISTRY; METALLURGY
    • C21—METALLURGY OF IRON
    • C21D—MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
    • C21D9/00—Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articles; Furnaces therefor
    • C21D9/50—Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articles; Furnaces therefor for welded joints
    • C—CHEMISTRY; METALLURGY
    • C21—METALLURGY OF IRON
    • C21D—MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
    • C21D9/00—Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articles; Furnaces therefor
    • C21D9/50—Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articles; Furnaces therefor for welded joints
    • C21D9/505—Cooling thereof
    • C—CHEMISTRY; METALLURGY
    • C21—METALLURGY OF IRON
    • C21D—MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
    • C21D1/00—General methods or devices for heat treatment, e.g. annealing, hardening, quenching or tempering
    • C21D1/34—Methods of heating
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/10—Water tubes; Accessories therefor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
    • F22B1/025—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group with vertical U shaped tubes carried on a horizontal tube sheet
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention relates to a nuclear electric heat treatment technology, and relates to a control technology for preventing a pit from being generated in a heat exchange tube during a heat treatment process of a nuclear steam generator, and particularly relates to a nuclear steam generator ring seam heat treatment device system and the use thereof.
  • the nuclear steam generator includes an upper assembly 10 having an upper annular seam 11 and a lower assembly 20 having a corresponding lower annular slit 21.
  • the upper annular gap 11 and the lower annular slit 21 require local heat treatment.
  • Nuclear power steam generators have high design requirements and complex manufacturing, and have special technical requirements in the local heat treatment process of key ring joints. Due to the large size and complicated structure of the steam generator, it is necessary to eliminate the welding residual stress during heat treatment, and to prevent the uneven expansion of the thermal expansion between the components during the heat treatment, which may cause the support plate to deform and may cause the heat exchange tube to be permanently indented. . To this end, effective control techniques must be employed to prevent pits from appearing in the heat exchange tubes during local heat treatment of the ring seam.
  • Preventing the pit control technology of the heat exchange tube can prevent the pits caused by permanent indentation during the heat treatment process on the one hand, and the successful application of this technology can optimize the steam generator manufacturing process, thereby greatly shortening the whole process.
  • the manufacturing sequence of the final two annular seams can be respectively carried out in two ways.
  • the method 1 firstly butt the upper annular joint 11 and then the lower annular joint 21, and the second method: firstly docking the lower annular joint 21, The upper annular seam 11 is butted.
  • the steam generator manufacturing sequence adopts the mode 2, that is, the method of first butting the lower annular seam 21 and then the upper annular joint 11.
  • the upper components are mostly structural parts, and the materials are mostly made of carbon steel or stainless steel.
  • the manufacturing is simple and can be purchased out.
  • the manufacturing cycle is short, and the welding conditions are first provided.
  • the lower head assembly in the lower assembly has a complicated structure and many manufacturing processes. , welding and machining work is large, and the manufacturing cycle is long. If the manufacturing sequence of mode 1 can be performed, the entire manufacturing cycle of the steam generator can be shortened by 6 months. However, Mode 1 increases the risk of pits in the heat exchange tubes. The difficulty of the system has also increased greatly.
  • the present invention provides a nuclear power steam generator annular seam heat treatment device system, the system comprising:
  • a temperature and flow controllable hot air venting device connected to the opening in the steam generator housing
  • a displacement measuring system for measuring an edge displacement of a support plate of the steam generator
  • the non-destructive testing device is used for eddy current detection and analysis of at least 20 heat exchange tubes around the support plate before and after the heat treatment to confirm whether the heat transfer tube has pits.
  • the above-mentioned nuclear power steam generator circumferential seam heat treatment device system wherein the heat treatment device comprises: an electric heating plate, a heat insulating material, a thermocouple and an electric heating numerical control system.
  • the heat treatment apparatus further comprises an electric heating plate fixing device and a heat insulating material fixing device.
  • the nuclear power steam generator circumferential seam heat treatment device system wherein the flow controllable cold air ventilation device comprises a cooling device, a ventilation pipe, a flow control cabinet, and a flow meter.
  • the above-mentioned nuclear power steam generator circumferential seam heat treatment device system wherein the cooling device has a maximum air flow of at least 10000 m 3 /h, and the flow rate can be adjusted steplessly during use.
  • the above-mentioned nuclear steam generator annular seam heat treatment device system wherein the temperature and flow controllable hot air ventilation device comprises a heating device, a ventilation pipe, a flow control cabinet, a temperature control cabinet, a flow meter, and an electric heater.
  • the above-mentioned nuclear steam generator annular seam heat treatment device system wherein the heating device has a maximum air flow of at least 10000 m 3 /h, and the flow rate can be adjusted steplessly during use.
  • the above-mentioned nuclear steam generator ring seam heat treatment device system wherein the electric heater is still the most
  • the low power is 20KW and the maximum temperature is adjusted to 250°C.
  • thermocouples to detect temperatures in different regions of the steam generator.
  • the invention also provides the use of the nuclear power steam generator circumferential seam heat treatment device system, wherein the nuclear steam generator circumferential seam comprises an upper annular seam and a lower annular seam, the system is used for a nuclear steam generator manufacturing process, the process First dock the upper ring seam and then the lower ring seam.
  • the nuclear electric steam generator annular seam heat treatment device system provided by the invention can be used for the nuclear steam generator manufacturing process (the process first butts the upper annular joint and then the lower annular joint), which not only prevents uneven thermal expansion between the components, but also supports the support.
  • the deformation of the plate may cause pits caused by permanent indentation in the heat exchange tubes, and the system can optimize the steam generator manufacturing process, thereby greatly shortening the manufacturing cycle of the entire steam generator.
  • FIG. 1 is a schematic view showing the position of a steam generator ring seam of the prior art.
  • FIG. 2 is a schematic view showing the position of a connection interface of a cooling device in a partial heat treatment process of the upper annular groove 11 of the nuclear power steam generator of the present invention.
  • Figure 3 is a cross-sectional view of the U1, U2 interface portion of Figure 2.
  • FIG. 4 is a schematic view showing the position of the connection interface of the heating and cooling device in the partial heat treatment process of the lower annular joint 21 of the nuclear power steam generator of the present invention.
  • the ring seam heat treatment process requires a complete set of heat treatment equipment, flow controllable cold air ventilation, temperature and flow controllable hot air ventilation, displacement measurement system, temperature monitoring system and nondestructive testing equipment. Wait.
  • the heat treatment equipment includes an electric heating plate, a heat insulating material, a thermocouple, an electric heating numerical control system, an electric heating plate fixing device, a heat insulating material fixing device, and the like.
  • the flow controllable cold air ventilation device comprises a cooling device, a ventilation duct, a flow control cabinet, a flow meter, and the like.
  • the device is connected to the opening in the steam generator housing during the heat treatment to blow in cold air or to extract hot air.
  • the maximum air flow of the cooling equipment is at least 10000m 3 /h, and the flow can be adjusted steplessly during the process.
  • the temperature and flow controllable hot air ventilation device comprises a heating device, a ventilation pipe, a flow control cabinet, a temperature control cabinet, a flow meter, an electric heater and the like.
  • the device is connected to the opening in the steam generator housing during the heat treatment to blow in hot air.
  • the maximum air flow rate of the heating equipment is at least 10000m 3 /h, and the air flow and temperature during the process can be adjusted steplessly.
  • the electric heater has a minimum power of 20 kW and an adjustable maximum temperature of 250 °C.
  • the displacement measuring system uses a special measuring device to measure the edge displacement of the support plate.
  • the measuring device collects, monitors and analyzes the data via connected instruments.
  • Four measuring devices are arranged on the edge of the support plate, wherein two measuring devices are arranged through two inspection holes on the steam generator, and two measuring devices are arranged perpendicularly thereto.
  • the temperature detecting system comprises a plurality of thermocouples. During the heat treatment process, different numbers of thermocouples are arranged in the heat exchange tubes, in the hand holes, and in the inspection holes to detect the temperature in different regions, and provide data for effectively controlling the flow of cold and hot air. stand by.
  • the non-destructive testing device is used for eddy current detection and analysis of at least 20 heat exchange tubes around the support plate of the steam generator before and after the heat treatment to confirm whether the heat transfer tube has pits, and whether the control technology is successful.
  • the flow controllable cold air ventilation device and the temperature and flow controllable hot air ventilation device are connected to the heating and cooling device connection interfaces (R1, S1, S2, T1, T2, U1) U2, U3, U4) See Fig. 2 and Fig. 3, wherein the U1 ⁇ U4 interfaces are evenly distributed on the circumference of the steam generator housing, and the distribution is schematically shown in Fig. 3. See Table 1 for the opening or closing of specific connection interfaces and interfaces during heat treatment. Any of the ten solutions shown in Table 1 can achieve the effect, and devices A, B, and C are cooling devices, and the devices are connected to the corresponding interfaces in Table 1.
  • the utility model provides a nuclear electric steam generator annular seam heat treatment device system, which is used for firstly butting the upper annular joint, and then docking the lower annular joint nuclear power steam generator manufacturing process, by controlling the number of heating equipment and cooling equipment used, connecting interface and interface Open or close the application parameters of the use timing, heating equipment and cooling equipment, the maximum displacement of the edge of the support plate, etc.; not only can prevent the uneven expansion of thermal expansion between the components, resulting in deformation of the support plate, which may cause permanent indentation of the heat exchange tube.
  • the pits in addition, the system optimizes the steam generator manufacturing process, thereby greatly reducing the manufacturing cycle of the entire steam generator.

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Mechanical Engineering (AREA)
  • Thermal Sciences (AREA)
  • Organic Chemistry (AREA)
  • Materials Engineering (AREA)
  • Metallurgy (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • General Engineering & Computer Science (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat Treatment Of Articles (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)

Abstract

A heat treatment device system for a circular seam of a nuclear power steam generator and the use thereof. The system includes a heat treatment apparatus, a flow-controllable cold wind ventilator, a temperature- and flow-controllable hot wind ventilator, a displacement measuring system, a temperature detection system, and a non-destructive testing apparatus. During the manufacturing process of the nuclear power steam generator, the heat treatment device system for the circular seam of the nuclear power steam generator could be used to dock the upper circular steam (11) firstly, and then the lower circular steam (21). The system can not only prevent the emergence of pits caused by permanent impressions in heat exchange tubes, but also optimize the manufacturing process of the steam generator, and therefore reduce the whole manufacturing cycle of the steam generator.

Description

一种核电蒸汽发生器环缝热处理装置***及其用途Nuclear electric steam generator ring seam heat treatment device system and use thereof 技术领域Technical field
本发明涉及核电热处理技术，涉及一种核电蒸汽发生器环缝热处理过程中防止换热管出现凹坑的控制技术，具体涉及一种核电蒸汽发生器环缝热处理装置***及其用途。The invention relates to a nuclear electric heat treatment technology, and relates to a control technology for preventing a pit from being generated in a heat exchange tube during a heat treatment process of a nuclear steam generator, and particularly relates to a nuclear steam generator ring seam heat treatment device system and the use thereof.
背景技术Background technique
如图1所示，核电蒸汽发生器包含上部组件10和下部组件20，该上部组件10具有上部环缝11，该下部组件20具有对应的下部环缝21。在核电蒸汽发生器制造工艺中，上部环缝11、下部环缝21均需局部热处理。As shown in FIG. 1, the nuclear steam generator includes an upper assembly 10 having an upper annular seam 11 and a lower assembly 20 having a corresponding lower annular slit 21. In the nuclear steam generator manufacturing process, the upper annular gap 11 and the lower annular slit 21 require local heat treatment.
核电蒸汽发生器设计要求高、制造复杂，关键环缝局部热处理工序中有着特殊技术要求。由于蒸汽发生器尺寸较大且结构复杂，热处理时既需要消除焊接残余应力，又需要防止热处理时各部件间热膨胀不均匀导致支承板变形而可能使换热管出现永久性压痕造成的凹坑。为此，必须采取有效的控制技术，防止环缝局部热处理中换热管出现凹坑。Nuclear power steam generators have high design requirements and complex manufacturing, and have special technical requirements in the local heat treatment process of key ring joints. Due to the large size and complicated structure of the steam generator, it is necessary to eliminate the welding residual stress during heat treatment, and to prevent the uneven expansion of the thermal expansion between the components during the heat treatment, which may cause the support plate to deform and may cause the heat exchange tube to be permanently indented. . To this end, effective control techniques must be employed to prevent pits from appearing in the heat exchange tubes during local heat treatment of the ring seam.
防止换热管出现凹坑控制技术一方面可以防止换热管在热处理过程中出现永久性压痕造成的凹坑，另一方面此技术的成功应用可以优化蒸汽发生器制造工艺，从而大大缩短整个蒸汽发生器的制造周期。蒸汽发生器的制造过程中，最终两条环缝的制造顺序可分别采用两种方式，方式1：先对接上部环缝11，后对接下部环缝21，方式2：先对接下部环缝21，后对接上部环缝11。现有技术中，国内外同类制造厂，蒸汽发生器制造顺序均采用方式2即先对接下部环缝21，后对接上部环缝11的方式。然而，上部组件多为结构件，材料多以碳钢或不锈钢为主，制造简单且可以外购，制造周期短，首先具备装焊条件；下部组件中的下封头组件结构复杂，制造工序繁多，焊接和机加工工作量大，制造周期长。若能执行方式1的制造顺序，可使蒸汽发生器的整个制造周期缩短6个月。但方式1使换热管出现凹坑的风险增加，控 制难度同时也大大增加。Preventing the pit control technology of the heat exchange tube can prevent the pits caused by permanent indentation during the heat treatment process on the one hand, and the successful application of this technology can optimize the steam generator manufacturing process, thereby greatly shortening the whole process. The manufacturing cycle of the steam generator. In the manufacturing process of the steam generator, the manufacturing sequence of the final two annular seams can be respectively carried out in two ways. The method 1: firstly butt the upper annular joint 11 and then the lower annular joint 21, and the second method: firstly docking the lower annular joint 21, The upper annular seam 11 is butted. In the prior art, in the similar manufacturing plants at home and abroad, the steam generator manufacturing sequence adopts the mode 2, that is, the method of first butting the lower annular seam 21 and then the upper annular joint 11. However, the upper components are mostly structural parts, and the materials are mostly made of carbon steel or stainless steel. The manufacturing is simple and can be purchased out. The manufacturing cycle is short, and the welding conditions are first provided. The lower head assembly in the lower assembly has a complicated structure and many manufacturing processes. , welding and machining work is large, and the manufacturing cycle is long. If the manufacturing sequence of mode 1 can be performed, the entire manufacturing cycle of the steam generator can be shortened by 6 months. However, Mode 1 increases the risk of pits in the heat exchange tubes. The difficulty of the system has also increased greatly.
因此，针对方式1(即，先对接上部环缝，再对接下部环缝的蒸汽发生器加工工艺)需要研发一种可以有效防止换热管出现凹坑的控制技术。Therefore, for the mode 1 (that is, the steam generator processing process of first docking the upper ring seam and then docking the lower ring seam), it is necessary to develop a control technology that can effectively prevent the heat pipe from appearing in the pit.
发明的公开Disclosure of invention
本发明的目的是提供一种能用于先对接上部环缝，再对接下部环缝的蒸汽发生器加工工艺的环缝热处理技术，其能防止换热管出现凹坑。SUMMARY OF THE INVENTION It is an object of the present invention to provide a circumferential seam heat treatment technique which can be used for the steam generator processing process of first butting the upper annular joint and then butting the lower annular joint, which can prevent the heat transfer tube from being pitted.
为达到上述目的，本发明提供了一种核电蒸汽发生器环缝热处理装置***，该***包含：To achieve the above object, the present invention provides a nuclear power steam generator annular seam heat treatment device system, the system comprising:
热处理设备，Heat treatment equipment,
与蒸汽发生器壳体上的开孔连接的流量可控冷风通风装置，a flow-controlled cold ventilating device connected to the opening in the steam generator housing,
与蒸汽发生器壳体上的开孔连接的温度及流量可控的热风通风装置；a temperature and flow controllable hot air venting device connected to the opening in the steam generator housing;
位移测量***，用于测量蒸汽发生器的支撑板的边缘位移；a displacement measuring system for measuring an edge displacement of a support plate of the steam generator;
温度检测***；及Temperature detection system; and
无损检测设备，用于在热处理前后分别对支撑板周边至少20根换热管进行涡流检测对比分析，以确认换热管是否出现凹坑。The non-destructive testing device is used for eddy current detection and analysis of at least 20 heat exchange tubes around the support plate before and after the heat treatment to confirm whether the heat transfer tube has pits.
上述的核电蒸汽发生器环缝热处理装置***，其中，所述的热处理设备包含：电加热板、保温材料、热电偶及电加热数控***。The above-mentioned nuclear power steam generator circumferential seam heat treatment device system, wherein the heat treatment device comprises: an electric heating plate, a heat insulating material, a thermocouple and an electric heating numerical control system.
进一步地，所述的热处理设备还包含电加热板固定装置、保温材料固定装置。Further, the heat treatment apparatus further comprises an electric heating plate fixing device and a heat insulating material fixing device.
上述的核电蒸汽发生器环缝热处理装置***，其中，所述的流量可控冷风通风装置包含冷却设备、通风管道、流量控制柜、流量测定仪。The nuclear power steam generator circumferential seam heat treatment device system, wherein the flow controllable cold air ventilation device comprises a cooling device, a ventilation pipe, a flow control cabinet, and a flow meter.
上述的核电蒸汽发生器环缝热处理装置***，其中，所述的冷却设备最大空气流量至少10000m3/h，使用过程中能无级调整流量。The above-mentioned nuclear power steam generator circumferential seam heat treatment device system, wherein the cooling device has a maximum air flow of at least 10000 m 3 /h, and the flow rate can be adjusted steplessly during use.
上述的核电蒸汽发生器环缝热处理装置***，其中，所述的温度及流量可控的热风通风装置包括加热设备、通风管道、流量控制柜、温度控制柜、流量测定仪、电加热器。The above-mentioned nuclear steam generator annular seam heat treatment device system, wherein the temperature and flow controllable hot air ventilation device comprises a heating device, a ventilation pipe, a flow control cabinet, a temperature control cabinet, a flow meter, and an electric heater.
上述的核电蒸汽发生器环缝热处理装置***，其中，所述的加热设备最大空气流量至少10000m3/h，使用过程中能无级调整流量。The above-mentioned nuclear steam generator annular seam heat treatment device system, wherein the heating device has a maximum air flow of at least 10000 m 3 /h, and the flow rate can be adjusted steplessly during use.
上述的核电蒸汽发生器环缝热处理装置***，其中，所还的电加热器最 小功率为20KW，调节最高温度为250℃。The above-mentioned nuclear steam generator ring seam heat treatment device system, wherein the electric heater is still the most The low power is 20KW and the maximum temperature is adjusted to 250°C.
上述的核电蒸汽发生器环缝热处理装置***，其中，所述的支撑板的边缘位移转换成角度最大不能超过1.5°。The nuclear power steam generator circumferential seam heat treatment device system described above, wherein the edge displacement of the support plate is converted to an angle of at most 1.5°.
上述的核电蒸汽发生器环缝热处理装置***，其中，所述的温度检测***包含若干热电偶，以检测蒸汽发生器不同区域的温度。The nuclear power steam generator circumferential seam heat treatment device system described above, wherein the temperature detecting system comprises a plurality of thermocouples to detect temperatures in different regions of the steam generator.
本发明还提供了一种上述的核电蒸汽发生器环缝热处理装置***的用途，该核电蒸汽发生器环缝包含上部环缝和下部环缝，该***用于核电蒸汽发生器制造工艺，该工艺先对接上部环缝，再对接下部环缝。The invention also provides the use of the nuclear power steam generator circumferential seam heat treatment device system, wherein the nuclear steam generator circumferential seam comprises an upper annular seam and a lower annular seam, the system is used for a nuclear steam generator manufacturing process, the process First dock the upper ring seam and then the lower ring seam.
本发明提供的核电蒸汽发生器环缝热处理装置***，能用于核电蒸汽发生器制造工艺(该工艺先对接上部环缝，再对接下部环缝)，不仅能防止各部件间热膨胀不均匀导致支承板变形而可能使换热管出现永久性压痕造成的凹坑，而且，该***可以优化蒸汽发生器制造工艺，从而大大缩短整个蒸汽发生器的制造周期。The nuclear electric steam generator annular seam heat treatment device system provided by the invention can be used for the nuclear steam generator manufacturing process (the process first butts the upper annular joint and then the lower annular joint), which not only prevents uneven thermal expansion between the components, but also supports the support. The deformation of the plate may cause pits caused by permanent indentation in the heat exchange tubes, and the system can optimize the steam generator manufacturing process, thereby greatly shortening the manufacturing cycle of the entire steam generator.
附图的简要说明BRIEF DESCRIPTION OF THE DRAWINGS
图1为现有技术的蒸汽发生器环缝位置示意图。1 is a schematic view showing the position of a steam generator ring seam of the prior art.
图2为本发明的核电蒸汽发生器的上部环缝11局部热处理工艺中，冷却设备连接接口位置示意图。2 is a schematic view showing the position of a connection interface of a cooling device in a partial heat treatment process of the upper annular groove 11 of the nuclear power steam generator of the present invention.
图3为图2中U1、U2接口部的截面图。Figure 3 is a cross-sectional view of the U1, U2 interface portion of Figure 2.
图4为本发明的核电蒸汽发生器的下部环缝21局部热处理工艺中，加热和冷却设备连接接口位置示意图。4 is a schematic view showing the position of the connection interface of the heating and cooling device in the partial heat treatment process of the lower annular joint 21 of the nuclear power steam generator of the present invention.
实现本发明的最佳方式The best way to implement the invention
以下结合附图对本发明的技术方案作进一步的说明。The technical solution of the present invention will be further described below with reference to the accompanying drawings.
为实现防止换热管出现凹坑，环缝热处理工艺需要一套完整的热处理设备、流量可控冷风通风装置、温度及流量可控的热风通风装置、位移测量***、温度监测***以及无损检测设备等。In order to prevent the occurrence of pits in the heat exchange tube, the ring seam heat treatment process requires a complete set of heat treatment equipment, flow controllable cold air ventilation, temperature and flow controllable hot air ventilation, displacement measurement system, temperature monitoring system and nondestructive testing equipment. Wait.
所述的热处理设备包括电加热板、保温材料、热电偶、电加热数控***、电加热板固定装置、保温材料固定装置等。The heat treatment equipment includes an electric heating plate, a heat insulating material, a thermocouple, an electric heating numerical control system, an electric heating plate fixing device, a heat insulating material fixing device, and the like.
所述的流量可控冷风通风装置包括冷却设备、通风管道、流量控制柜、 流量测定仪等。在热处理过程中该装置连接蒸汽发生器壳体上的开孔，吹入冷空气或抽出热空气。冷却设备最大空气流量至少10000m3/h，过程中可无级调整流量。The flow controllable cold air ventilation device comprises a cooling device, a ventilation duct, a flow control cabinet, a flow meter, and the like. The device is connected to the opening in the steam generator housing during the heat treatment to blow in cold air or to extract hot air. The maximum air flow of the cooling equipment is at least 10000m 3 /h, and the flow can be adjusted steplessly during the process.
所述的温度及流量可控的热风通风装置包括加热设备、通风管道、流量控制柜、温度控制柜、流量测定仪、电加热器等。在热处理过程中该装置连接蒸汽发生器壳体上的开孔，吹入热空气。加热设备最大空气流量至少10000m3/h，过程中空气流量和温度可无级调整。电加热器最小功率为20KW，调节最高温度为250℃。The temperature and flow controllable hot air ventilation device comprises a heating device, a ventilation pipe, a flow control cabinet, a temperature control cabinet, a flow meter, an electric heater and the like. The device is connected to the opening in the steam generator housing during the heat treatment to blow in hot air. The maximum air flow rate of the heating equipment is at least 10000m 3 /h, and the air flow and temperature during the process can be adjusted steplessly. The electric heater has a minimum power of 20 kW and an adjustable maximum temperature of 250 °C.
所述的位移测量***采用特殊的测量设备测量支撑板的边缘位移。测量设备通过相连接的仪器进行数据收集、监控和分析。4个测量设备布置在支撑板边缘，其中2个测量设备通过蒸汽发生器上的2个检查孔布置，2个测量设备与之垂直布置。The displacement measuring system uses a special measuring device to measure the edge displacement of the support plate. The measuring device collects, monitors and analyzes the data via connected instruments. Four measuring devices are arranged on the edge of the support plate, wherein two measuring devices are arranged through two inspection holes on the steam generator, and two measuring devices are arranged perpendicularly thereto.
所述的温度检测***包含若干热电偶，热处理过程中不同数量的热电偶分别布置在换热管内、手孔内、检查孔内，以检测不同区域的温度，为有效控制冷、热风流量提供数据支持。The temperature detecting system comprises a plurality of thermocouples. During the heat treatment process, different numbers of thermocouples are arranged in the heat exchange tubes, in the hand holes, and in the inspection holes to detect the temperature in different regions, and provide data for effectively controlling the flow of cold and hot air. stand by.
所述的无损检测设备，用于热处理前后分别对蒸汽发生器的支撑板周边至少20根换热管进行涡流检测对比分析，以确认换热管是否出现凹坑，控制技术是否成功。The non-destructive testing device is used for eddy current detection and analysis of at least 20 heat exchange tubes around the support plate of the steam generator before and after the heat treatment to confirm whether the heat transfer tube has pits, and whether the control technology is successful.
环缝局部热处理前安装上述所有设备。热处理过程中，通过支撑板边缘位移的监测结果、不同位置热电偶的温度监测结果来调节冷热风流量和温度，以及蒸汽发生器壳体上开孔的打开和关闭时机。最终通过换热管的涡流检测结果判断防止换热管出现凹坑的控制技术是否应用成功。热处理过程中按支撑板边缘位移转换成的角度最大不能超过1.5°进行控制。Install all of the above equipment before the local heat treatment of the ring seam. During the heat treatment, the hot and cold air flow and temperature are adjusted by the monitoring results of the displacement of the edge of the support plate and the temperature monitoring results of the thermocouples at different positions, and the opening and closing timing of the opening on the steam generator housing. Finally, it is judged whether the control technology for preventing the occurrence of pits in the heat exchange tube is successfully applied by the eddy current detection result of the heat exchange tube. During the heat treatment, the angle converted by the edge displacement of the support plate cannot be more than 1.5° for control.
本发明的蒸汽发生器上部环缝11局部热处理时，流量可控冷风通风装置和温度及流量可控热风通风装置中的加热和冷却设备连接接口位置(R1、S1、S2、T1、T2、U1、U2、U3、U4)见图2及图3，其中，U1～U4接口均匀分布位于蒸汽发生器壳体的圆周上，分布示意如图3所示。热处理过程中具体的连接接口和接口的打开或关闭情况见表1。表1所示十种方案中的任意一种均可达到效果，设备A、B、C均为冷却设备，该设备与表1中的相应接口连接。 When the upper annular groove 11 of the steam generator of the present invention is partially heat treated, the flow controllable cold air ventilation device and the temperature and flow controllable hot air ventilation device are connected to the heating and cooling device connection interfaces (R1, S1, S2, T1, T2, U1) U2, U3, U4) See Fig. 2 and Fig. 3, wherein the U1~U4 interfaces are evenly distributed on the circumference of the steam generator housing, and the distribution is schematically shown in Fig. 3. See Table 1 for the opening or closing of specific connection interfaces and interfaces during heat treatment. Any of the ten solutions shown in Table 1 can achieve the effect, and devices A, B, and C are cooling devices, and the devices are connected to the corresponding interfaces in Table 1.
表1：上部环缝11换热管凹坑防护方案Table 1: Upper ring joint 11 heat exchange tube pit protection scheme
Figure PCTCN2014001169-appb-000001
Figure PCTCN2014001169-appb-000001
蒸汽发生器下部环缝21局部热处理时，流量可控冷风通风装置和温度及流量可控热风通风装置中的加热和冷却设备连接接口位置(R1、S1、S2、T1、T2、U1、U2、U3、U4)见图3、图4，热处理过程中具体的连接接口和接口的打开或关闭情况见表2。表2所示十种方案中的任意一种均可达到效果，A、B1、B2为冷却设备，C为加热设备，该设备与表2中的相应接口连接。 When the steam generator lower annular seam 21 is partially heat treated, the flow controllable cold air ventilation device and the temperature and flow controllable hot air ventilation device in the heating and cooling device connection interface position (R1, S1, S2, T1, T2, U1, U2) U3, U4) See Figure 3, Figure 4, the specific connection interface and interface opening or closing during heat treatment are shown in Table 2. Any of the ten solutions shown in Table 2 can achieve the effect, A, B1, B2 are cooling devices, and C is a heating device, which is connected to the corresponding interface in Table 2.
表2：下部环缝21换热管凹坑防护方案Table 2: Lower ring seam 21 heat exchange tube pit protection scheme
Figure PCTCN2014001169-appb-000002
Figure PCTCN2014001169-appb-000002
注：表2中的“/”表示该连接设备的接口处于关闭状态。Note: “/” in Table 2 indicates that the interface of the connected device is off.
本发明提供的核电蒸汽发生器环缝热处理装置***，用于先对接上部环缝，再对接下部环缝的核电蒸汽发生器制造工艺，通过控制加热设备和冷却设备的使用数量、连接接口、接口打开或关闭使用时机、加热设备和冷却设备的应用参数，支撑板边缘位移的最大限度等；不仅能防止各部件间热膨胀不均匀导致支承板变形而可能使换热管出现永久性压痕造成的凹坑，而且，该***可以优化蒸汽发生器制造工艺，从而大大缩短整个蒸汽发生器的制造周期。The utility model provides a nuclear electric steam generator annular seam heat treatment device system, which is used for firstly butting the upper annular joint, and then docking the lower annular joint nuclear power steam generator manufacturing process, by controlling the number of heating equipment and cooling equipment used, connecting interface and interface Open or close the application parameters of the use timing, heating equipment and cooling equipment, the maximum displacement of the edge of the support plate, etc.; not only can prevent the uneven expansion of thermal expansion between the components, resulting in deformation of the support plate, which may cause permanent indentation of the heat exchange tube. The pits, in addition, the system optimizes the steam generator manufacturing process, thereby greatly reducing the manufacturing cycle of the entire steam generator.
尽管本发明的内容已经通过上述优选实施例作了详细介绍，但应当认识到上述的描述不应被认为是对本发明的限制。在本领域技术人员阅读了上述内容后，对于本发明的多种修改和替代都将是显而易见的。因此，本发明的保护范围应由所附的权利要求来限定。 Although the present invention has been described in detail by the preferred embodiments thereof, it should be understood that the foregoing description should not be construed as limiting. Various modifications and alterations of the present invention will be apparent to those skilled in the art. Therefore, the scope of the invention should be defined by the appended claims.

Claims (10)

  1. 一种核电蒸汽发生器环缝热处理装置***，其特征在于，该***包含：A nuclear steam generator annular seam heat treatment device system, characterized in that the system comprises:
    热处理设备，Heat treatment equipment,
    流量可控冷风通风装置，Flow controllable cold air ventilation,
    温度及流量可控的热风通风装置；Temperature and flow controllable hot air ventilation device;
    位移测量***，用于测量蒸汽发生器的支撑板的边缘位移；a displacement measuring system for measuring an edge displacement of a support plate of the steam generator;
    温度检测***；及Temperature detection system; and
    无损检测设备，用于在热处理前后分别对支撑板周边至少20根换热管进行涡流检测对比分析，以确认换热管是否出现凹坑。The non-destructive testing device is used for eddy current detection and analysis of at least 20 heat exchange tubes around the support plate before and after the heat treatment to confirm whether the heat transfer tube has pits.
  2. 如权利要求1所述的核电蒸汽发生器环缝热处理装置***，其特征在于，所述的热处理设备包含：电加热板、保温材料、热电偶及电加热数控***。The nuclear power steam generator circumferential seam heat treatment device system according to claim 1, wherein the heat treatment device comprises: an electric heating plate, a heat insulating material, a thermocouple, and an electric heating numerical control system.
  3. 如权利要求1所述的核电蒸汽发生器环缝热处理装置***，其特征在于，所述的流量可控冷风通风装置包含冷却设备、通风管道、流量控制柜、流量测定仪。The nuclear power steam generator circumferential seam heat treatment device system according to claim 1, wherein the flow controllable cold air ventilation device comprises a cooling device, a ventilation duct, a flow control cabinet, and a flow meter.
  4. 如权利要求3所述的核电蒸汽发生器环缝热处理装置***，其特征在于，A nuclear steam generator annular seam heat treatment device system according to claim 3, wherein
    i.所述的冷却设备最大空气流量至少10000m3/h，使用过程中能无级调整流量。i. The cooling device has a maximum air flow of at least 10000 m 3 /h, and the flow rate can be adjusted steplessly during use.
  5. 如权利要求1所述的核电蒸汽发生器环缝热处理装置***，其特征在于，所述的温度及流量可控的热风通风装置包括加热设备、通风管道、流量控制柜、温度控制柜、流量测定仪、电加热器。The nuclear power steam generator circumferential seam heat treatment device system according to claim 1, wherein said temperature and flow controllable hot air ventilation device comprises heating equipment, ventilation duct, flow control cabinet, temperature control cabinet, flow measurement Instrument, electric heater.
  6. 如权利要求5所述的核电蒸汽发生器环缝热处理装置***，其特征在于，所述的加热设备最大空气流量至少10000m3/h，使用过程中能无级调整流量。A nuclear power steam generator circumferential seam heat treatment device system according to claim 5, wherein said heating device has a maximum air flow of at least 10,000 m 3 /h, and the flow rate can be adjusted steplessly during use.
  7. 如权利要求5所述的核电蒸汽发生器环缝热处理装置***，其特征在于，所述的电加热器最小功率为20KW，调节最高温度为250℃。A nuclear steam generator circumferential seam heat treatment device system according to claim 5, wherein said electric heater has a minimum power of 20 kW and an adjusted maximum temperature of 250 °C.
  8. 如权利要求1所述的核电蒸汽发生器环缝热处理装置***，其特征在于，所述的支撑板的边缘位移转换成角度最大不能超过1.5°。The nuclear power steam generator circumferential seam heat treatment device system according to claim 1, wherein the edge displacement of said support plate is converted to an angle of at most 1.5°.
  9. 如权利要求1所述的核电蒸汽发生器环缝热处理装置***，其特征在于， 所述的温度检测***包含若干热电偶，以检测蒸汽发生器不同区域的温度。A nuclear steam generator circumferential seam heat treatment device system according to claim 1, wherein The temperature sensing system includes a plurality of thermocouples to detect temperatures in different regions of the steam generator.
  10. 一种根据权利要求1所述的核电蒸汽发生器环缝热处理装置***的用途，该核电蒸汽发生器环缝包含上部环缝(11)和下部环缝环(21)，其特征在于，该***用于核电蒸汽发生器制造工艺，该工艺先对接上部环缝(11)，再对接下部环缝(21)。 A use of a nuclear steam generator circumferential seam heat treatment device system according to claim 1, the nuclear steam generator annular seam comprising an upper annular seam (11) and a lower annular seam (21), characterized in that the system It is used in the nuclear steam generator manufacturing process, which firstly butts the upper annular joint (11) and then the lower annular joint (21).
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