WO2016122104A1 - Heat insulating material mounting structure of steam generator of two-loop type pressurized light water reactor - Google Patents

Heat insulating material mounting structure of steam generator of two-loop type pressurized light water reactor Download PDF

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Publication number
WO2016122104A1
WO2016122104A1 PCT/KR2015/013370 KR2015013370W WO2016122104A1 WO 2016122104 A1 WO2016122104 A1 WO 2016122104A1 KR 2015013370 W KR2015013370 W KR 2015013370W WO 2016122104 A1 WO2016122104 A1 WO 2016122104A1
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Prior art keywords
steam generator
support
insulating material
heat insulating
skirt support
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PCT/KR2015/013370
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French (fr)
Korean (ko)
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문인득
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문인득
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/16Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/20Partitions or thermal insulation between fuel channel and moderator
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • the present invention relates to a facility for insulating a steam generator provided in the reactor coolant system equipment, and more particularly, insulators, heat shields and a plurality of insulation cylinders in the stay cylinder and skirt support of the reactor steam generator.
  • insulators By using the supporting plate made of pieces to closely adhere the insulation to the lower part of the steam generator, the sagging of the insulation is completely prevented due to the vibration during the operation of the reactor, so that the high temperature of the steam generator is applied to the stagnated air area
  • the present invention relates to a thermal insulation material mounting structure of a pressurized water reactor-type nuclear power plant steam generator for effectively preventing transmission to the sliding base and preventing structural vibration of the reactor coolant system according to thermal expansion deformation of the sliding base.
  • nuclear power plants in Korea for example, Conversetion Engineering (CE) System Plus 80 (Hanbit 3, 4), Korean standard nuclear power plants (Hanul 3, 4, 5, 6 and Hanbit 5, 6), OPR1000 (Shin-Gori 1,2), APR1400 (Shin-Gori 3,4, Shin-Uljin 1,2, UAE Nuclear Power Plants 1-4), 2-loop Pressurized Water Reactor.
  • CE Conversetion Engineering
  • reactor coolant system
  • Such a reactor (1) is described in the Republic of Korea Patent Publication No. 10-1473665, "Pipe support device for replacing parts of nuclear power plant", the reactor coolant system (RC: Reactor Coolant System (RCS) 3: in the containment building 2) Is provided.
  • RC Reactor Coolant System
  • This reactor coolant system 3 has a reactor 5 containing a reactor and two heat transfer circuits 7 connected thereto.
  • FIG. 1 two heat transfer circuits are shown connected in parallel to the reactor 5.
  • Each circuit 7 comprises a steam generator 9 and at least one coolant pump 11 for circulating coolant between the reactor 5 and the steam generator 9.
  • Each circuit 7 includes three main pipes, the main pipe having a large diameter, connected to the main parts of the circuit.
  • the circuit 7 includes a pressurizer 18 to keep the temperature and pressure of the coolant constant.
  • the first large diameter tubing or hot leg 13 is connected to one side of the reactor 5 and the inlet side of the coolant chamber of the steam generator 9 to be in contact with the core in the reactor 5.
  • the heated coolant is sent to a steam generator (9).
  • the circulation pipe 15 called a cross-over leg connects one side of the discharge part of the coolant chamber of the steam generator 9 and one side of the vortex chamber suction part of the coolant pump 11.
  • the cold leg 17 connects between the vortex chamber of the coolant pump 11 and the reactor 5.
  • the coolant cooled in the steam generator 9 and drawn out by the coolant pump 11 is transferred to the reactor 5 through the circulation pipe 15 and the low temperature pipe 7 to cool the core.
  • each steam generator 9 has a substructure as shown in FIG. 2.
  • the steam generator 9 has a stay cylinder 21 which is maintained at a high temperature, and a skirt support 23 of a cylindrical structure that supports it at the bottom thereof.
  • Such a skirt support 23 is fixed and supported by the stud bolt 32 on the sliding base 30 of the lower side, such a sliding base 30 is a forged anchor plate (40) And a plurality of, for example, four hemispherical sliders 42 provided on the bearing plate 41 to accommodate movement in response to thermal expansion occurring during operation of the reactor 1.
  • the heat insulating material 50 is generally disposed on the lower surface of the stay cylinder 21, and the cross-shaped (+) is formed to closely contact the stay cylinder 21 side. This is to utilize the insulation support 60 having the support arms (62).
  • the heat insulating material support 60 is the lower end is fixed to the sliding plate 30, the upper surface of the cruciform support arms 62 support the heat insulating material 50 to the stay cylinder 21 in close contact.
  • a hole is formed in the heat insulating material 50, and the heat insulating material 50 is formed by using a fixing member, for example, a plurality of mounting pins 70.
  • thermal insulation material mounting structure causes a problem that the thermal insulation material 50 sags downwardly over time due to vibration generated during operation of the reactor 1.
  • the conventional heat insulating material mounting structure is not a structure that firmly tightly adheres the heat insulating material 50 to the bottom surface of the stay cylinder 21, it is not a structure that holds it as a whole, and as time passes, a part of the heat insulating material 50 is lowered The lower surface of the stay cylinder 21 is exposed.
  • the thermal insulation material 50 in the staganated air area 80 between the steam generator skirt support 23 and the sliding base 30 of the reactor 1 is installed in the coolant piping of the reactor.
  • the local factor and vibration cause local dropout.
  • the final connection welding of the intermediate tube and the steam generator nozzle is left as a residual load on the sliding base 30 and the pump vertical support due to the welding shrinkage.
  • settlement of the sliding base 30 due to welding shrinkage occurs, and settlement typically occurs in the range of about 1 mm after installation of the steam generator 9 and after final connection welding.
  • This settlement can be seen as a load remaining in the sliding base 30, the residual load is characterized by increasing the frictional force on the sliding base 30 in the initial stage of the reactor 1 to inhibit the sliding operation in the lateral direction. .
  • the thermal transfer (copy) phenomenon occurs locally in the sliding base 30 to increase the thermal deformation, usually the thermal insulation material (50)
  • a high temperature of about 300 ° C. is transferred from the stay cylinder 21 to the sliding base 30 to cause thermal stress, and causes thermal deformation problems of the sliding base 30.
  • Such thermal deformation suppresses free movement due to thermal expansion of the sliding base 30 generated during operation of the nuclear power plant, or causes interference with surrounding structures on the upper part of the steam generator 9, and consequently, the steam generator 9 and the coolant pump. It causes structural vibration of (11).
  • the steam generator 9 is inclined to operate as a result of the thermal deformation, and even after stopping at room temperature, a phenomenon in which the parts are shifted may appear in succession.
  • An object of the present invention is to solve the conventional problems as described above, by improving the support structure of the thermal insulation material installed on the skirt support (skirt support) by reinforcing the structure to prevent the insulation material from falling, sliding base (sliding base) and A thermal insulation mounting structure of a nuclear reactor steam generator can be prevented from rising in the stagnated air area between skirt supports to prevent thermal deformation of the sliding base.
  • Another object of the present invention is to completely prevent local sagging of the thermal insulation material due to vibration of the facility during operation of the reactor, and to maintain the high temperature of the steam generator through the thermal insulation gap through the stagnated air area of the lower portion. It is to effectively prevent the transfer to the sliding base, to provide a heat insulating material mounting structure of the steam generator for preventing the occurrence of vibration of the reactor (1) due to the thermal expansion deformation of the sliding base.
  • the present invention in the thermal insulation material mounting structure for preventing the thermal expansion deformation of the lower side sliding base by blocking the high heat transmitted from the steam generator provided in the reactor 1, the stay of the steam generator A heat insulating material disposed along the lower surface of the cylinder and the inner upper surface of the skirt support; And a support plate disposed along a connection portion of the stay cylinder and the skirt support and having a plurality of fixing bolts penetrating outwardly from the inner space of the skirt support to tightly fix the insulation to the bottom surface of the stay cylinder.
  • the support plate is made of a plurality of pieces, the support plate is made of an arcuate structure along the connecting portion of the stay cylinder and the skirt support It provides a heat insulating material mounting structure of the steam generator.
  • the circumference formed by the connecting portion of the stay cylinder and the skirt support it has a circumferential angle of 90 degrees, and four are disposed throughout the circumference and fixed along the entire rim of the insulation.
  • the support plate is each machined and manufactured in a curved cross-sectional structure corresponding to the contour formed by the connection portion of the stay cylinder and the skirt support, the connection portion of the stay cylinder and the skirt support With respect to the circumference to be formed, a bolt ball is formed at a circumferential angle of 30 degrees so that the fixing bolt is mounted.
  • the present invention is preferably, the fixing bolt is disposed so that the head portion is disposed in the inner space of the skirt support to penetrate the support plate, the insulation and the skirt support from the inner space of the skirt support to the outside, the skirt support
  • the penetrating threaded portion is fitted with a large diameter washer machined to have a surface coincident with the contour of the skirt support on the outside of the skirt support, and each fixed with a nut.
  • the heat insulating material is further provided with a heat shielding plate disposed to be in close contact with the entire lower surface, the heat shielding plate is fixed with a fixing bolt between the heat insulating material and the support plate to the heat insulating material of the stay cylinder It is in close contact with the bottom surface.
  • the heat shield plate is formed with a rim of the curved cross-section whose edge coincides with the contour formed by the connecting portion of the stay cylinder and the skirt support, when joining with the support plate, This is in close contact with each other.
  • a heat shield plate disposed in close contact with the surface of the sliding base, it is configured to prevent the transfer of radiant heat to the sliding base.
  • the heat insulating material is disposed along the bottom surface of the stay cylinder of the steam generator and the inner top surface of the skirt support, and the heat insulating material is closely adhered to the bottom surface of the stay cylinder by using a heat shield plate and a support plate made of a plurality of pieces. Fix it.
  • these support plates are each secured through a number of fastening bolts penetrating outward from the inner space of the skirt support, and through large diameter washers and nuts machined to have a surface coincident with the contour of the skirt support outside the skirt support. It is fixed.
  • the present invention during the operation of the reactor 1, it is possible to completely prevent the local sagging of the thermal insulation material due to the vibration of the installation, the high heat of the steam generator is sliding through the stagnated air area of the lower An improved effect can be obtained that completely prevents the transfer to the base, thereby minimizing thermal expansion deformation of the sliding base.
  • FIG. 1 is an explanatory diagram showing a configuration of a reactor 1 facility of a general nuclear power plant.
  • Figure 2 is a cross-sectional view for explaining a heat insulating material mounting structure of the steam generator according to the prior art.
  • FIG. 3A is an explanatory view showing a structure in which a heat insulating material support having a cruciform support arm supports a heat insulating material at a lower part of a stay cylinder in a heat insulating material mounting structure of a steam generator according to the related art.
  • 3B is an explanatory view showing a structure in which a hole is formed in the heat insulating material in the steam generator according to the related art, and the heat insulating material is in close contact with the bottom surface of the stay cylinder by using mounting pins.
  • FIG. 4 is a cross-sectional view illustrating a heat insulating material mounting structure of the steam generator according to the present invention.
  • FIG. 5 is an exploded cross-sectional view showing a component configuration of the heat insulating material mounting structure of the steam generator according to the present invention.
  • Figure 6 is a perspective view of the components of the heat insulating material mounting structure of the steam generator according to the present invention, respectively showing the configuration of the heat insulating material, the heat shield plate and a plurality of support plates.
  • Figure 7 is an enlarged cross-sectional view showing a coupling cross section of the heat insulating material mounting structure of the steam generator according to the present invention.
  • the thermal insulation material mounting structure 100 of the steam generator according to the present invention in the lower portion of the steam generator 9 provided in the reactor 1, from the steam generator 9 to the lower By blocking the high heat transmitted to the, it is to effectively prevent the thermal expansion deformation of the lower side sliding base (30).
  • the heat insulating material mounting structure 100 of the steam generator according to the present invention includes a heat insulating material 110 disposed along the lower surface of the stay cylinder 21 of the reactor steam generator 9 and the inner upper surface of the skirt support 23.
  • the heat insulating material 110 may be formed of a felt-type structure covering the entire lower surface of the stay cylinder 21.
  • the heat shield plate 120 is provided on the lower surface of the thermal insulation material 110, such a heat shield plate 120 of the thermal insulation material 110 It is a disk-shaped structure arranged in close contact with the whole in the lower surface.
  • the structure of the heat insulating material 110 and the heat shield plate 120 is shown in detail as an exploded view in FIG.
  • the heat insulating material 110 is made of a circular structure that corresponds to the circular lower surface of the stay cylinder 21, the heat shield plate 120 is a disc structure corresponding to the heat insulating material 110 in the lower portion of the heat insulating material (110) Is done.
  • the heat shield plate 120 forms an edge of a curved cross section whose edge 122 coincides with a contour formed by the connection portion of the stay cylinder 21 and the skirt support 23.
  • the edge of the mold cross section achieves excellent results in that when the joining of the plurality of support plates 130 described below, the joining surfaces coincide with each other and are closely joined to each other.
  • the thermal insulation material mounting structure 100 of the reactor steam generator according to the present invention is disposed along the connecting portion of the stay cylinder 21 and the skirt support 23, the thermal insulation material 110 on the lower surface of the stay cylinder 21; It includes a support plate 130 consisting of a plurality of pieces to closely adhere to the.
  • Each of the support plates 130 is made of steel having an arc-shaped curved cross section, and the heat insulating material 110 and the heat through the plurality of fixing bolts 140 penetrating outward from the inner space of the skirt support 23.
  • the blocking plate 120 is integrally fixed to the lower surface of the stay cylinder 21.
  • Each of the support plates 130 has an arc-shaped structure
  • the curvature of the arc-shaped structure is a circle along the connecting portion of the stay cylinder 21 and the skirt support 23 Match the arc-like structure, or curvature.
  • the support plates 130 preferably have a circumferential angle ⁇ 1 of 90 degrees with respect to the circumference formed by the connecting portion of the stay cylinder 21 and the skirt support 23, and four of the circumferences. It is disposed throughout and fixed along the entire edge of the thermal insulation (110).
  • the support plate 130 is machined and manufactured in a curved cross-sectional structure corresponding to the contour formed by the connecting portion of the stay cylinder 21 and the skirt support 23, respectively.
  • a plurality of bolt balls 132 are formed and fixed at a circumferential angle ⁇ 2 of 30 degrees with respect to the circumference formed by the connection portion of the stay cylinder 21 and the skirt support 23.
  • Bolt 140 is mounted.
  • the fixing bolt 140 is arranged to penetrate outward from the inner space of the skirt support 23, such fixing bolt 140 is shown in detail in cross section in Figure 7, the head portion 142 is the It is disposed in the inner space of the skirt support 23 is disposed so as to pass through the support plate 130, the heat insulating material 110 and the skirt support 23 sequentially from the inner space of the skirt support 23.
  • the fixing bolt 140 is fixed to the threaded portion penetrating the skirt support 23 with the washer 144 and the nut 146 on the outside of the skirt support 23, such a washer 144 is a skirt support It consists of a large diameter washer 144 machined to have a surface consistent with the contour of 23, thereby effectively distracting the pulling stress of the fixing bolt 140 and allowing it to be more stably fixed by the nut 146.
  • Insulating material mounting structure 100 of the reactor steam generator according to the present invention configured as described above, as shown in the exploded view in Figure 5, arranging the insulating material 110 on the lower surface of the stay cylinder 21, heat shielding plate After the 120 is in close contact with the lower surface of the heat insulating material 110, the plurality of supporting plates 130 are disposed along the lower surface of the edge of the heat shield plate 120, and then using a plurality of fixing bolts 140 It is fixed to the skirt support (23).
  • the heat insulating material 110 is fixed using the plurality of support plates 130 as described above, as shown in FIG. 4, the heat insulating material 110 is disposed on the entire bottom surface of the stay cylinder 21. It is in close contact by the state, the edge 112 of the heat insulating material 110 is firmly fixed to the connection portion of the stay cylinder 21 and the skirt support 23 over the entire circumferential direction by the support plates 130.
  • the outer side of the skirt support 23 is fitted with a large diameter washer 144 machined to have a surface matching the contour of the skirt support 23, thereby more effectively dispersing the pull stress of the fixing bolt 140,
  • the nut 146 is to be more stably fixed.
  • the heat insulating material 110 is tightly fixed to the lower surface of the stay cylinder 21 of the steam generator 9, the heat insulating material 110 is also caused by vibration generated during operation of the reactor 1.
  • the local sag of) can be completely prevented.
  • the high heat of approximately 300 ° C. generated in the steam generator 9 can be effectively prevented from radiating transfer to the stagnated air area under the stay cylinder 21, thereby preventing heating of the sliding base 30. It is possible to minimize the thermal expansion deformation of the sliding base 30 as a result, and to achieve an excellent effect that can be stably operated by minimizing vibration of the reactor 1 facility.
  • the support plates 130 may be arranged along a circumference formed by the connecting portion of the stay cylinder 21 and the skirt support 23 in the form of a plurality of pieces, not more than four pieces, or two or three or five or more shapes. It may be a structure that becomes.
  • the fixing bolts 140 may also fix the support plates 130 through various arrangement intervals.
  • the heat shield plate 120 has been described with a single layer disc structure, it is a matter of course that the heat shield plate 120 may be formed of a plurality of layers or a plate layer structure of multiple layers.
  • a heat shield plate may be installed on the sliding base surface to prevent radiant heat from being transferred to the sliding base. Nevertheless, such simple design modifications or variations will be made clear in advance that all obviously fall within the scope of the present invention.

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  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

A heat insulating material mounting structure of a steam generator of the present invention, for preventing the thermal expansion deformation of a sliding base below the steam generator by blocking the heat transferred from the steam generator provided in a nuclear reactor (1), comprises: a heat insulating material disposed along the lower surface of a stay cylinder of the steam generator and the upper inner surface of a skirt support; and a support plate that is disposed along the connection portion between the stay cylinder and the skirt support and includes a plurality of pieces for closely fixing the heat insulating material to the lower surface of the stay cylinder with a plurality of fixing bolts that pass through the skirt support from the inside to the outside thereof, thereby preventing the deflection of the heat insulating material, which is caused by vibration while the nuclear reactor (1) is being operated.

Description

2-루프 가압경수로형의 증기 발생기의 보온재 장착구조Insulation structure of 2-loop pressurized water reactor steam generator
본 발명은 원자로냉각재계통설비에 구비된 증기 발생기를 보온하기 위한 설비에 관한 것으로, 보다 상세히는 원자로 증기 발생기의 스테이 실린더(Stay cylinder) 와 스커트 지지대(skirt support) 부분에서 보온재, 열차단판과 다수의 조각편으로 이루어진 지지 플레이트를 활용하여 증기 발생기의 하부를 따라 보온재를 밀착 고정시킴으로써 원자로의 운전중 진동에 따른 보온재의 처짐을 완벽하게 방지하여 증기 발생기의 고열이 하부의 공기 정체 구역(stagnated air area)을 통해 슬라이딩 베이스로 전달되는 것을 효과적으로 방지하고, 슬라이딩 베이스의 열팽창 변형에 따른 원자로냉각재계통설비의 구조적 진동 발생현상을 방지하기 위한 가압경수로형 원전 증기 발생기의 보온재 장착구조에 관한 것이다.The present invention relates to a facility for insulating a steam generator provided in the reactor coolant system equipment, and more particularly, insulators, heat shields and a plurality of insulation cylinders in the stay cylinder and skirt support of the reactor steam generator. By using the supporting plate made of pieces to closely adhere the insulation to the lower part of the steam generator, the sagging of the insulation is completely prevented due to the vibration during the operation of the reactor, so that the high temperature of the steam generator is applied to the stagnated air area The present invention relates to a thermal insulation material mounting structure of a pressurized water reactor-type nuclear power plant steam generator for effectively preventing transmission to the sliding base and preventing structural vibration of the reactor coolant system according to thermal expansion deformation of the sliding base.
일반적으로, 원자력 발전소는 국내의 예를 들면, 컨버스천 엔지니어링(Conbustion Engineering :CE)의 시스템플러스 80(한빛 3,4호기), 한국 표준형 원전(한울3,4,5,6호기 및 한빛 5,6호기), OPR1000(신고리 1,2호기), APR1400(신고리 3,4호기, 신울진 1,2호기, UAE 원전 1~4호기), 2-루프 가압경수로(Pressurized Water Reactor)등이 있다. In general, nuclear power plants in Korea, for example, Conversetion Engineering (CE) System Plus 80 (Hanbit 3, 4), Korean standard nuclear power plants (Hanul 3, 4, 5, 6 and Hanbit 5, 6), OPR1000 (Shin-Gori 1,2), APR1400 (Shin-Gori 3,4, Shin-Uljin 1,2, UAE Nuclear Power Plants 1-4), 2-loop Pressurized Water Reactor.
도 1을 참조하면, 이러한 원자로냉각재계통설비(이하, 간략히 "원자로"라 한다)의 기본 구조가 도시되어 있다.Referring to Figure 1, the basic structure of such a reactor coolant system (hereinafter referred to simply as "reactor") is shown.
이와 같은 원자로(1)는 대한민국 등록특허공보 제10-1473665호의 "원자력 발전소의 부품 교체용 배관 지지 장치"에도 기재된 바와 같이, 격납 건물(2) 내에 원자로 냉각재 계통(3: RCS: Reactor Coolant System)이 구비된다. Such a reactor (1) is described in the Republic of Korea Patent Publication No. 10-1473665, "Pipe support device for replacing parts of nuclear power plant", the reactor coolant system (RC: Reactor Coolant System (RCS) 3: in the containment building 2) Is provided.
이와 같은 원자로 냉각재 계통(3)은 원자로를 담고 있는 반응기(5)와, 이에 연결된 두개의 열전달 회로(7)를 가진다. This reactor coolant system 3 has a reactor 5 containing a reactor and two heat transfer circuits 7 connected thereto.
도 1에서는 두 개의 열전달 회로가 반응기(5)에 병렬로 연결된 것이 도시되어 있다. In FIG. 1, two heat transfer circuits are shown connected in parallel to the reactor 5.
각 회로(7)는 증기 발생기(9)와, 반응기(5) 및 증기 발생기(9) 사이에서 냉각재를 순환시키는 적어도 하나의 냉각재 펌프(11)를 포함한다. 각 회로(7)는 3개의 메인 배관을 포함하고, 메인 배관은 대구경으로 마련되며, 회로의 주요 부품과 연결된다. 이에 더하여 회로(7)는 냉각재의 온도 및 압력을 일정하게 유지하도록 하는 가압기(18)를 포함한다. Each circuit 7 comprises a steam generator 9 and at least one coolant pump 11 for circulating coolant between the reactor 5 and the steam generator 9. Each circuit 7 includes three main pipes, the main pipe having a large diameter, connected to the main parts of the circuit. In addition, the circuit 7 includes a pressurizer 18 to keep the temperature and pressure of the coolant constant.
첫 번째 대구경 배관 또는 고온관(hot leg)(13)은 반응기(5)의 일측과, 증기 발생기(9)의 냉각재 챔버의 흡입부 일측에 연결되어 반응기(5) 내의 노심(core)과 접촉되어 가열된 냉각재를 증기 발생기(9)로 전송한다. The first large diameter tubing or hot leg 13 is connected to one side of the reactor 5 and the inlet side of the coolant chamber of the steam generator 9 to be in contact with the core in the reactor 5. The heated coolant is sent to a steam generator (9).
크로스 오버 레그(cross-over leg)로 불리는 순환관(15)은 증기 발생기(9)의 냉각재 챔버의 토출부 일측 및 냉각재 펌프(11)의 와류실 흡입부 일측을 연결한다. The circulation pipe 15 called a cross-over leg connects one side of the discharge part of the coolant chamber of the steam generator 9 and one side of the vortex chamber suction part of the coolant pump 11.
그리고, 저온관(Cold leg)(17)은 냉각재 펌프(11)의 와류실과 반응기(5) 사이를 연결한다. 또한, 증기 발생기(9)에서 냉각되고 냉각재 펌프(11)에 의해 인출된 냉각재는 순환관(15), 저온관(7)을 통하여 반응기(5)로 전송되어 노심을 냉각한다. The cold leg 17 connects between the vortex chamber of the coolant pump 11 and the reactor 5. In addition, the coolant cooled in the steam generator 9 and drawn out by the coolant pump 11 is transferred to the reactor 5 through the circulation pipe 15 and the low temperature pipe 7 to cool the core.
이와 같은 원자로(1)에서, 각각의 증기 발생기(9)는, 도 2에 도시된 바와 같은 하부 구조를 갖는다.In such a reactor 1, each steam generator 9 has a substructure as shown in FIG. 2.
즉, 증기 발생기(9)는 고온 상태로 유지되는 스테이 실린더(Stay cylinder)(21)를 구비하고, 그 하부에서 이를 떠받치는 원통형 구조의 스커트 지지대(skirt support)(23)를 구비한다.That is, the steam generator 9 has a stay cylinder 21 which is maintained at a high temperature, and a skirt support 23 of a cylindrical structure that supports it at the bottom thereof.
이와 같은 스커트 지지대(23)는 그 하부측의 슬라이딩 베이스(30) 상에 스터드 볼트(32)에 의해서 고정되어 지지되며, 이와 같은 슬라이딩 베이스(30)는 포지드 앵커 플레이트(Forged Anchor Plate)(40)와 베어링 플레이트(41)상에 마련된 다수의, 예를 들면 4개의 반구형 슬라이더(42) 상에서 지지되어 원자로(1)의 운전중에 발생하는 열팽창에 대응하여 움직임을 수용하도록 되어 있다. Such a skirt support 23 is fixed and supported by the stud bolt 32 on the sliding base 30 of the lower side, such a sliding base 30 is a forged anchor plate (40) And a plurality of, for example, four hemispherical sliders 42 provided on the bearing plate 41 to accommodate movement in response to thermal expansion occurring during operation of the reactor 1.
또한, 이와 같은 증기 발생기(9)는 운전중에 고열이 발생하므로, 이와 같은 고열이 하부의 슬라이딩 베이스(30)로 전달되는 것을 방지하기 위한 보온재(50)를 스테이 실린더(21)의 하부면과, 스커트 지지대(23) 부분에 장착하고 있다.In addition, since the high temperature is generated during operation of the steam generator 9, the lower surface of the stay cylinder 21 and the heat insulating material 50 for preventing such high heat from being transmitted to the sliding base 30 of the lower part, It is attached to the skirt support 23 part.
종래의 보온재 장착구조가 도 3a 및 도 3b에 상세히 도시되어 있다.Conventional thermal insulation material mounting structure is shown in detail in Figures 3a and 3b.
즉, 종래의 보온재 장착구조는 도 3a에 도시된 바와 같이, 스테이 실린더(21)의 하부면에 보온재(50)를 전체적으로 배치시키고, 이를 스테이 실린더(21) 측으로 밀착시키기 위하여 열십자형(+)의 지지 암(62)들을 갖는 보온재 지지대(60)를 활용하는 방식이다.That is, in the conventional heat insulating material mounting structure, as shown in FIG. 3A, the heat insulating material 50 is generally disposed on the lower surface of the stay cylinder 21, and the cross-shaped (+) is formed to closely contact the stay cylinder 21 side. This is to utilize the insulation support 60 having the support arms (62).
이와 같은 보온재 지지대(60)는 그 하단부가 슬라이딩 플레이트(30)에 고정되고, 상부면은 열십자형의 지지 암(62)들이 보온재(50)를 스테이 실린더(21) 측으로 밀착 지지한다.The heat insulating material support 60 is the lower end is fixed to the sliding plate 30, the upper surface of the cruciform support arms 62 support the heat insulating material 50 to the stay cylinder 21 in close contact.
또는, 다른 방식으로는, 도 3b에 도시된 바와 같이, 보온재(50)에 구멍을 형성하고, 고정 부재, 예를 들면 다수의 장착 핀(70)들을 활용하여 보온재(50)를 스테이 실린더(21)의 하부면에 밀착시키는 방식이다.Alternatively, as shown in FIG. 3B, a hole is formed in the heat insulating material 50, and the heat insulating material 50 is formed by using a fixing member, for example, a plurality of mounting pins 70. ) To the bottom surface of the
그러나, 이와 같은 종래의 보온재 장착구조들은, 원자로(1)의 운전중에 발생하는 진동으로 인하여 시간이 경과하면서, 보온재(50)가 국소적으로 하부로 처지는 문제점을 발생시킨다.However, such a conventional thermal insulation material mounting structure causes a problem that the thermal insulation material 50 sags downwardly over time due to vibration generated during operation of the reactor 1.
즉, 종래의 보온재 장착구조는 보온재(50)를 스테이 실린더(21)의 하부면에 견고히 완전 밀착시키고, 이를 전체적으로 떠받치는 구조가 아니어서 시간이 경과하면서, 보온재(50)의 일부가 하부로 처지고, 스테이 실린더(21)의 하부면을 노출시킨다.That is, the conventional heat insulating material mounting structure is not a structure that firmly tightly adheres the heat insulating material 50 to the bottom surface of the stay cylinder 21, it is not a structure that holds it as a whole, and as time passes, a part of the heat insulating material 50 is lowered The lower surface of the stay cylinder 21 is exposed.
이와 같이 보온재(50)가 처져서 스테이 실린더(21)의 하부면이 노출되면, 이를 통해서 스테이 실린더(21)의 고열이 스커트 지지대(23)의 내측 원통형 공기 정체 구역(stagnated air area)(80)으로 복사 전달되고, 이를 통해서 슬라이딩 베이스(30)를 가열시켜서 심각한 열변형을 초래하는 문제점이 있다.In this way, when the insulation 50 sags and the lower surface of the stay cylinder 21 is exposed, high heat of the stay cylinder 21 is transferred to the inner cylindrical stagnated air area 80 of the skirt support 23. Radiation is transmitted, thereby heating the sliding base 30 causes a serious thermal deformation.
이에 관련된 문제점이 아래에 상세하게 기재되어 있다.Problems related to this are described in detail below.
즉, 원자로(1)의 증기 발생기 스커트 지지대(23)와 슬라이딩 베이스(Sliding Base) 사이(30)의 공기 정체 구역(staganated air area)(80)에 있는 보온재(50)는 원자로의 냉각재 배관의 시공적인 요인과, 진동에 의해 국부적 탈락이 생기게 된다. That is, the thermal insulation material 50 in the staganated air area 80 between the steam generator skirt support 23 and the sliding base 30 of the reactor 1 is installed in the coolant piping of the reactor. The local factor and vibration cause local dropout.
원자로 배관의 시공적 요인으로는, 중간관과 증기 발생기 노즐의 최종 연결용접이 용접 수축으로 인해 슬라이딩 베이스(30)와 펌프 수직 지지대에 잔류 하중으로 남게 된다. 이러한 잔류 하중의 결과로서, 용접 수축에 의한 슬라이딩 베이스(30)의 침하가 발생되며, 증기 발생기(9)의 설치 후와, 최종 연결 용접후에는 통상적으로 약 1mm 범위내의 침하가 발생한다. As a construction factor of the reactor piping, the final connection welding of the intermediate tube and the steam generator nozzle is left as a residual load on the sliding base 30 and the pump vertical support due to the welding shrinkage. As a result of this residual load, settlement of the sliding base 30 due to welding shrinkage occurs, and settlement typically occurs in the range of about 1 mm after installation of the steam generator 9 and after final connection welding.
이러한 침하량이 슬라이딩 베이스(30)에 잔류하는 하중으로 볼 수 있으며, 이러한 잔류 하중은 원자로(1)의 기동 초기에 슬라이딩 베이스(30)에 마찰력을 증가시켜서 횡방향의 미끌림 작동을 저해하는 특성이 있다.This settlement can be seen as a load remaining in the sliding base 30, the residual load is characterized by increasing the frictional force on the sliding base 30 in the initial stage of the reactor 1 to inhibit the sliding operation in the lateral direction. .
또한, 원자로(1)의 운전 중에 발생하는 진동으로 인하여 보온재(50)에 틈새가 발생하면, 슬라이딩 베이스(30)에 국부적으로 열전달(복사) 현상이 생겨서 열적 변형을 가중시키게 되는데, 통상 보온재(50) 틈새로 약 300℃의 고열이 스테이 실린더(21)로부터 슬라이딩 베이스(sliding base)(30)로 전달되어 열응력을 일으키고, 슬라이딩 베이스(30)의 열적변형 문제점을 야기시킨다. In addition, when a gap occurs in the thermal insulation material 50 due to the vibration generated during the operation of the reactor (1), the thermal transfer (copy) phenomenon occurs locally in the sliding base 30 to increase the thermal deformation, usually the thermal insulation material (50) A high temperature of about 300 ° C. is transferred from the stay cylinder 21 to the sliding base 30 to cause thermal stress, and causes thermal deformation problems of the sliding base 30.
이러한 열적변형은 원자력 발전소 운전중 발생하는 슬라이딩 베이스(30)의 열팽창에 따른 자유로운 이동을 억제하거나, 증기 발생기(9) 상부의 주변 구조물과 간섭을 발생시키고, 결과적으로 증기 발생기(9)와 냉각재 펌프(11)의 구조적 진동을 유발시키게 된다. Such thermal deformation suppresses free movement due to thermal expansion of the sliding base 30 generated during operation of the nuclear power plant, or causes interference with surrounding structures on the upper part of the steam generator 9, and consequently, the steam generator 9 and the coolant pump. It causes structural vibration of (11).
결과적으로, 이러한 구조적 진동은 증기 발생기(9)의 세관 마모(wear)와 진동 응력(vibration stress)을 일으키고, 장주기 운전하면 붕산 누적으로 붕산취화 현상 있는 소구경 배관의 피로를 유발하여 붕산수 누설이 된다. As a result, this structural vibration causes the tubular wear and vibration stress of the steam generator 9, and in long cycle operation, boric acid accumulation causes boric acid embrittlement and fatigue of boron embrittlement in small diameter pipes, resulting in leakage of boric acid. .
뿐만 아니라, 슬라이딩 베이스(30)가 열변형되면, 그로 인해 증기 발생기(9)가 기울어져 운전되고, 상온 정지 후에도 부품간의 어긋남 현상이 연이어 나타날 수 있다.In addition, when the sliding base 30 is thermally deformed, the steam generator 9 is inclined to operate as a result of the thermal deformation, and even after stopping at room temperature, a phenomenon in which the parts are shifted may appear in succession.
이와 같이 슬라이딩 베이스(30)가 변형되어 수평을 유지 못하면, 증기 발생기(9)가 기울어지고, 결과적으로 원자로 냉각재 펌프(11)와 증기 발생기(9)의 관련 지지 구조물의 변형과 간섭으로 인해 진동응력(Vibration stress)을 더욱 가중시키게 된다.If the sliding base 30 is deformed and leveled as described above, the steam generator 9 is tilted, and as a result, the vibration stress due to the deformation and interference of the associated support structure of the reactor coolant pump 11 and the steam generator 9. This increases the (Vibration stress).
이러한 진동응력은 증기 발생기(9)의 세관 마모의 원인이 될 뿐만 아니라, 원자로 냉각재 펌프(11)의 내장품 마모, RCS 계통에 연결된 배관에 피로를 가중시켜서 피로 균열을 유발시키는 것이 해외 원자력 발전소 운전중 자주 발생되고 있다. This vibration stress causes not only the tubular wear of the steam generator 9, but also the wear of the internal parts of the reactor coolant pump 11 and the fatigue cracking caused by fatigue in the pipe connected to the RCS system. It happens frequently.
이러한 상태로 장주기 운전되면, 원자로 냉각재 펌프(11)의 메카니컬 실(mechnical seal)과 소구경 배관의 누설로 이어진다. Long period operation in such a state leads to the leakage of the mechanical seal of the reactor coolant pump 11 and the small diameter pipe.
따라서, 당 업계에서는 원자로(1)의 구조적 진동으로 인한 증기 발생기(9)의 세관 마모와, 원자로 냉각재 계통 설비의 마모(wear)를 방지할 수 있는 기술 개발이 절실하게 요구되는 실정이다.Therefore, there is an urgent need in the art for the development of a technology capable of preventing the wear of the steam generator 9 due to the structural vibration of the reactor 1 and the wear of the reactor coolant system equipment.
본 발명의 목적은 상기와 같은 종래의 문제점을 해소시키기 위한 것으로서, 스커트 지지대(skirt support)에 설치되는 보온재의 지지 구조를 개선하여 보온재 이탈을 방지하는 구조로 보강함으로써, 슬라이딩 베이스(sliding base)과 스커트 지지대(skirt support) 사이의 정체 공기 구역(stagnated air area)에서의 온도 상승을 방지하여 슬라이딩 베이스의 열 변형을 방지할 수 있는 원자로 증기 발생기의 보온재 장착구조를 제공하는 데 있다.An object of the present invention is to solve the conventional problems as described above, by improving the support structure of the thermal insulation material installed on the skirt support (skirt support) by reinforcing the structure to prevent the insulation material from falling, sliding base (sliding base) and A thermal insulation mounting structure of a nuclear reactor steam generator can be prevented from rising in the stagnated air area between skirt supports to prevent thermal deformation of the sliding base.
그리고, 본 발명의 다른 목적은, 원자로의 운전중에, 설비 진동에 따른 보온재의 국부적인 처짐을 완벽하게 방지하고, 보온재 틈새를 통하여 증기 발생기의 고열이 하부의 공기 정체 구역(stagnated air area)을 통해 슬라이딩 베이스로 전달되는 것을 효과적으로 방지하며, 슬라이딩 베이스의 열팽창 변형에 따른 원자로(1)의 진동 발생현상을 방지하기 위한 증기 발생기의 보온재 장착구조를 제공함에 있다. Another object of the present invention is to completely prevent local sagging of the thermal insulation material due to vibration of the facility during operation of the reactor, and to maintain the high temperature of the steam generator through the thermal insulation gap through the stagnated air area of the lower portion. It is to effectively prevent the transfer to the sliding base, to provide a heat insulating material mounting structure of the steam generator for preventing the occurrence of vibration of the reactor (1) due to the thermal expansion deformation of the sliding base.
상기와 같은 목적을 달성하기 위하여 본 발명은, 원자로(1)에 구비된 증기 발생기로부터 전달되는 고열을 차단하여, 하부측 슬라이딩 베이스의 열팽창 변형을 방지하기 위한 보온재 장착구조에 있어서, 증기 발생기의 스테이 실린더 하부면과 스커트 지지대의 내측 상부면을 따라서 배치되는 보온재; 및 상기 스테이 실린더와 스커트 지지대의 연결 부분을 따라서 배치되고, 상기 스커트 지지대의 내측 공간으로부터 외측으로 관통하는 다수의 고정 볼트들을 구비하여 스테이 실린더의 하부면에 보온재를 밀착 고정시키는 지지 플레이트;를 포함하여 원자로(1)의 운전중 진동에 따른 보온재의 처짐을 방지하도록 구성되고, 상기 지지 플레이트는 다수의 조각편으로 이루어지고, 상기 지지 플레이트는 상기 스테이 실린더와 스커트 지지대의 연결 부분을 따르는 원호형 구조로 이루어진 증기 발생기의 보온재 장착구조를 제공한다. In order to achieve the above object, the present invention, in the thermal insulation material mounting structure for preventing the thermal expansion deformation of the lower side sliding base by blocking the high heat transmitted from the steam generator provided in the reactor 1, the stay of the steam generator A heat insulating material disposed along the lower surface of the cylinder and the inner upper surface of the skirt support; And a support plate disposed along a connection portion of the stay cylinder and the skirt support and having a plurality of fixing bolts penetrating outwardly from the inner space of the skirt support to tightly fix the insulation to the bottom surface of the stay cylinder. It is configured to prevent sagging of the thermal insulation material due to vibration during operation of the reactor (1), wherein the support plate is made of a plurality of pieces, the support plate is made of an arcuate structure along the connecting portion of the stay cylinder and the skirt support It provides a heat insulating material mounting structure of the steam generator.
바람직하게는, 상기 스테이 실린더와 스커트 지지대의 연결 부분이 형성하는 원주에 대해, 90도의 원주각도를 구비하며, 4개가 상기 원주 전체에 배치되어 보온재의 테두리 전체를 따라서 고정된 것이다. Preferably, with respect to the circumference formed by the connecting portion of the stay cylinder and the skirt support, it has a circumferential angle of 90 degrees, and four are disposed throughout the circumference and fixed along the entire rim of the insulation.
또한 본 발명은 바람직하게는, 상기 지지 플레이트는 각각, 상기 스테이 실린더와 스커트 지지대의 연결 부분이 형성하는 윤곽에 일치하는 만곡형 단면 구조로 기계 가공되어 제작되고, 상기 스테이 실린더와 스커트 지지대의 연결 부분이 형성하는 원주에 대해, 30도의 원주 각도로 볼트 공이 형성되어 고정 볼트가 장착된 것이다.In addition, the present invention preferably, the support plate is each machined and manufactured in a curved cross-sectional structure corresponding to the contour formed by the connection portion of the stay cylinder and the skirt support, the connection portion of the stay cylinder and the skirt support With respect to the circumference to be formed, a bolt ball is formed at a circumferential angle of 30 degrees so that the fixing bolt is mounted.
그리고 본 발명은 바람직하게는, 상기 고정 볼트는 그 머리부가 상기 스커트 지지대의 내측 공간에 배치되어 상기 스커트 지지대의 내측 공간으로부터 지지 플레이트, 보온재 및 스커트 지지대를 외측으로 관통하도록 배치되고, 상기 스커트 지지대를 관통한 나사부는 스커트 지지대의 외측에서 스커트 지지대의 윤곽에 일치하는 표면을 갖도록 기계 가공된 대구경 와셔가 끼워지고, 너트로 각각 고정된 것이다.And the present invention is preferably, the fixing bolt is disposed so that the head portion is disposed in the inner space of the skirt support to penetrate the support plate, the insulation and the skirt support from the inner space of the skirt support to the outside, the skirt support The penetrating threaded portion is fitted with a large diameter washer machined to have a surface coincident with the contour of the skirt support on the outside of the skirt support, and each fixed with a nut.
또한 본 발명은 바람직하게는, 상기 보온재는 그 하부면 전체에 밀착하도록 배치된 열 차단판을 추가적으로 구비하고, 상기 열 차단판은 보온재와 지지 플레이트 사이에서 고정 볼트로 고정되어 상기 보온재를 스테이 실린더의 하부면에 밀착시키는 것이다.In addition, the present invention preferably, the heat insulating material is further provided with a heat shielding plate disposed to be in close contact with the entire lower surface, the heat shielding plate is fixed with a fixing bolt between the heat insulating material and the support plate to the heat insulating material of the stay cylinder It is in close contact with the bottom surface.
그리고 본 발명은 바람직하게는, 상기 열 차단판은 그 테두리가 상기 스테이 실린더와 스커트 지지대의 연결 부분이 형성하는 윤곽에 일치하는 만곡형 단면의 테두리로 형성되어 지지 플레이트와의 결합시, 그 결합 표면이 상호 일치하여 밀착 결합되는 것이다.And the present invention preferably, the heat shield plate is formed with a rim of the curved cross-section whose edge coincides with the contour formed by the connecting portion of the stay cylinder and the skirt support, when joining with the support plate, This is in close contact with each other.
바람직하게는, 상기 슬라이딩 베이스의 표면에 밀착되게 배치된 열 차단판을 더 구비하여, 슬라이딩 베이스로 복사열이 전달되는 것을 방지하도록 구성된다. Preferably, further comprising a heat shield plate disposed in close contact with the surface of the sliding base, it is configured to prevent the transfer of radiant heat to the sliding base.
본 발명에 의하면, 증기 발생기의 스테이 실린더 하부면과 스커트 지지대의 내측 상부면을 따라서 보온재가 배치되고, 열 차단판과, 다수의 조각편으로 이루어진 지지 플레이트를 이용하여 스테이 실린더의 하부면에 보온재를 밀착 고정시킨다. 또한, 이와 같은 지지 플레이트들은 스커트 지지대의 내측 공간으로부터 외측으로 관통하는 다수의 고정 볼트들과, 스커트 지지대의 외측에서 스커트 지지대의 윤곽에 일치하는 표면을 갖도록 기계 가공된 대구경 와셔 및 너트를 통해서 각각 견고하게 고정된 것이다.According to the present invention, the heat insulating material is disposed along the bottom surface of the stay cylinder of the steam generator and the inner top surface of the skirt support, and the heat insulating material is closely adhered to the bottom surface of the stay cylinder by using a heat shield plate and a support plate made of a plurality of pieces. Fix it. In addition, these support plates are each secured through a number of fastening bolts penetrating outward from the inner space of the skirt support, and through large diameter washers and nuts machined to have a surface coincident with the contour of the skirt support outside the skirt support. It is fixed.
따라서, 본 발명에 의하면, 원자로(1)의 운전중에, 설비 진동에 따른 보온재의 국부적인 처짐을 완벽하게 방지할 수 있으며, 증기 발생기의 고열이 하부의 공기 정체 구역(stagnated air area)을 통해 슬라이딩 베이스로 전달되는 것을 완벽하게 방지하여 슬라이딩 베이스의 열팽창 변형을 최소화시키는 개선된 효과가 얻어질 수 있다.Therefore, according to the present invention, during the operation of the reactor 1, it is possible to completely prevent the local sagging of the thermal insulation material due to the vibration of the installation, the high heat of the steam generator is sliding through the stagnated air area of the lower An improved effect can be obtained that completely prevents the transfer to the base, thereby minimizing thermal expansion deformation of the sliding base.
도 1은 일반적인 원자력 발전소의 원자로(1) 설비 구성을 도시한 설명도이다.1 is an explanatory diagram showing a configuration of a reactor 1 facility of a general nuclear power plant.
도 2는 종래의 기술에 따른 증기 발생기의 보온재 장착구조를 설명하기 위한 단면도이다.Figure 2 is a cross-sectional view for explaining a heat insulating material mounting structure of the steam generator according to the prior art.
도 3a는 종래의 기술에 따른 증기 발생기의 보온재 장착구조에서, 열십자형의 지지 암을 갖는 보온재 지지대가 스테이 실린더의 하부에서 보온재를 지지하는 구조를 도시한 설명도이다.3A is an explanatory view showing a structure in which a heat insulating material support having a cruciform support arm supports a heat insulating material at a lower part of a stay cylinder in a heat insulating material mounting structure of a steam generator according to the related art.
도 3b는 종래의 기술에 따른 증기 발생기의 보온재 장착구조에서, 보온재에 구멍을 형성하고, 장착 핀들을 활용하여 보온재를 스테이 실린더의 하부면에 밀착시키는 구조를 도시한 설명도이다.3B is an explanatory view showing a structure in which a hole is formed in the heat insulating material in the steam generator according to the related art, and the heat insulating material is in close contact with the bottom surface of the stay cylinder by using mounting pins.
도 4는 본 발명에 따른 증기 발생기의 보온재 장착구조를 도시한 결합 단면도이다.4 is a cross-sectional view illustrating a heat insulating material mounting structure of the steam generator according to the present invention.
도 5는 본 발명에 따른 증기 발생기의 보온재 장착구조의 부품 구성을 각각 도시한 분해 단면도이다.5 is an exploded cross-sectional view showing a component configuration of the heat insulating material mounting structure of the steam generator according to the present invention.
도 6은 본 발명에 따른 증기 발생기의 보온재 장착구조의 부품 중, 보온재, 열 차단판 및 다수의 지지 플레이트들의 구성을 각각 도시한 외관 사시도이다.Figure 6 is a perspective view of the components of the heat insulating material mounting structure of the steam generator according to the present invention, respectively showing the configuration of the heat insulating material, the heat shield plate and a plurality of support plates.
도 7은 본 발명에 따른 증기 발생기의 보온재 장착구조의 결합 단면을 도시한 확대 단면도이다.Figure 7 is an enlarged cross-sectional view showing a coupling cross section of the heat insulating material mounting structure of the steam generator according to the present invention.
이하, 본 발명의 바람직한 실시 예를 도면을 참조하여 보다 상세히 설명한다.Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the drawings.
본 발명에 따른 증기 발생기의 보온재 장착구조(100)는, 도 4 및 도 5에 전체적으로 도시된 바와 같이, 원자로(1)에 구비된 증기 발생기(9)의 하부에서, 증기 발생기(9)로부터 하부로 전달되는 고열을 차단하여, 하부측 슬라이딩 베이스(30)의 열팽창 변형을 효과적으로 방지하기 위한 것이다.The thermal insulation material mounting structure 100 of the steam generator according to the present invention, as shown in Figures 4 and 5 as a whole, in the lower portion of the steam generator 9 provided in the reactor 1, from the steam generator 9 to the lower By blocking the high heat transmitted to the, it is to effectively prevent the thermal expansion deformation of the lower side sliding base (30).
본 발명에 따른 증기 발생기의 보온재 장착구조(100)는, 원자로 증기 발생기(9)의 스테이 실린더(21) 하부면과 스커트 지지대(23)의 내측 상부면을 따라서 배치되는 보온재(110)를 구비하는데, 이와 같은 보온재(110)는 스테이 실린더(21)의 하부면 전체를 덮는 펠트(felt)형 구조로 이루어질 수 있다.The heat insulating material mounting structure 100 of the steam generator according to the present invention includes a heat insulating material 110 disposed along the lower surface of the stay cylinder 21 of the reactor steam generator 9 and the inner upper surface of the skirt support 23. The heat insulating material 110 may be formed of a felt-type structure covering the entire lower surface of the stay cylinder 21.
그리고 본 발명에 따른 원자로 증기 발생기의 보온재 장착구조(100)는, 상기 보온재(110)의 하부면에 열 차단판(120)을 구비하는데, 이와 같은 열 차단판(120)은 보온재(110)의 하부면에서 그 전체에 밀착하도록 배치된 원판형의 구조이다.And the thermal insulation material mounting structure 100 of the reactor steam generator according to the present invention, the heat shield plate 120 is provided on the lower surface of the thermal insulation material 110, such a heat shield plate 120 of the thermal insulation material 110 It is a disk-shaped structure arranged in close contact with the whole in the lower surface.
이와 같은 보온재(110)와 열 차단판(120)의 구조가 도 6에 분해도로서, 상세히 도시되어 있다.The structure of the heat insulating material 110 and the heat shield plate 120 is shown in detail as an exploded view in FIG.
즉, 상기 보온재(110)는 스테이 실린더(21)의 원형 하부면에 일치하는 원형 구조로 이루어지고, 열 차단판(120)은 보온재(110)의 하부에서 보온재(110)에 일치하는 원판 구조로 이루어진다.That is, the heat insulating material 110 is made of a circular structure that corresponds to the circular lower surface of the stay cylinder 21, the heat shield plate 120 is a disc structure corresponding to the heat insulating material 110 in the lower portion of the heat insulating material (110) Is done.
이와 같은 열 차단판(120)은, 그 테두리(122)가 상기 스테이 실린더(21)와 스커트 지지대(23)의 연결 부분이 형성하는 윤곽에 일치하는 만곡형 단면의 테두리를 형성하는데, 이와 같은 만곡형 단면의 테두리는, 이하에서 설명되는 다수의 지지 플레이트(130) 들과의 결합시, 그 결합 표면이 상호 일치하여 서로 밀착 결합되는 우수한 결과를 얻는다.The heat shield plate 120 forms an edge of a curved cross section whose edge 122 coincides with a contour formed by the connection portion of the stay cylinder 21 and the skirt support 23. The edge of the mold cross section achieves excellent results in that when the joining of the plurality of support plates 130 described below, the joining surfaces coincide with each other and are closely joined to each other.
또한, 본 발명에 따른 원자로 증기 발생기의 보온재 장착구조(100)는, 상기 스테이 실린더(21)와 스커트 지지대(23)의 연결 부분을 따라서 배치되어 스테이 실린더(21)의 하부면에 보온재(110)를 밀착 고정시키는 다수의 조각편으로 이루어진 지지 플레이트(130)를 포함한다.In addition, the thermal insulation material mounting structure 100 of the reactor steam generator according to the present invention is disposed along the connecting portion of the stay cylinder 21 and the skirt support 23, the thermal insulation material 110 on the lower surface of the stay cylinder 21; It includes a support plate 130 consisting of a plurality of pieces to closely adhere to the.
이와 같은 지지 플레이트(130)들은 각각 원호형의 만곡된 단면을 갖는 강재로 이루어지는데, 스커트 지지대(23)의 내측 공간으로부터 외측으로 관통하는 다수의 고정 볼트(140)들을 통하여 보온재(110)와 열 차단판(120)을 스테이 실린더(21)의 하부면에 일체로 고정시킨다.Each of the support plates 130 is made of steel having an arc-shaped curved cross section, and the heat insulating material 110 and the heat through the plurality of fixing bolts 140 penetrating outward from the inner space of the skirt support 23. The blocking plate 120 is integrally fixed to the lower surface of the stay cylinder 21.
상기 지지 플레이트(130)는 각각, 도 6에 도시된 바와 같이, 원호형의 구조로 이루어지는데, 이러한 원호형 구조의 곡률은 상기 스테이 실린더(21)와 스커트 지지대(23)의 연결 부분을 따르는 원호형 구조, 또는 곡률에 일치한다.Each of the support plates 130, as shown in Figure 6, has an arc-shaped structure, the curvature of the arc-shaped structure is a circle along the connecting portion of the stay cylinder 21 and the skirt support 23 Match the arc-like structure, or curvature.
또한, 이러한 지지 플레이트(130)들은 바람직하게는, 상기 스테이 실린더(21)와 스커트 지지대(23)의 연결 부분이 형성하는 원주에 대해, 90도의 원주 각도(θ1)를 구비하며, 4개가 상기 원주 전체에 배치되어 보온재(110)의 테두리 전체를 따라서 고정된다.In addition, the support plates 130 preferably have a circumferential angle θ1 of 90 degrees with respect to the circumference formed by the connecting portion of the stay cylinder 21 and the skirt support 23, and four of the circumferences. It is disposed throughout and fixed along the entire edge of the thermal insulation (110).
그리고 이러한 지지 플레이트(130)는 각각, 상기 스테이 실린더(21)와 스커트 지지대(23)의 연결 부분이 형성하는 윤곽에 일치하는 만곡형 단면 구조로 기계 가공되어 제작된다.The support plate 130 is machined and manufactured in a curved cross-sectional structure corresponding to the contour formed by the connecting portion of the stay cylinder 21 and the skirt support 23, respectively.
또한, 도 6에 도시된 바와 같이, 상기 스테이 실린더(21)와 스커트 지지대(23)의 연결 부분이 형성하는 원주에 대해, 30도의 원주 각도(θ2)로 볼트 공(132)들이 다수 형성되어 고정 볼트(140)가 장착된다.6, a plurality of bolt balls 132 are formed and fixed at a circumferential angle θ2 of 30 degrees with respect to the circumference formed by the connection portion of the stay cylinder 21 and the skirt support 23. Bolt 140 is mounted.
상기 고정 볼트(140)는 스커트 지지대(23)의 내측 공간으로부터 외측으로 관통하도록 배치되는데, 이와 같은 고정 볼트(140)는 도 7에 단면으로 상세히 도시된 바와 같이, 그 머리부(142)가 상기 스커트 지지대(23)의 내측 공간에 배치되어 상기 스커트 지지대(23)의 내측 공간으로부터 순차적으로 지지 플레이트(130), 보온재(110) 및 스커트 지지대(23)를 외측으로 관통하도록 배치된다.The fixing bolt 140 is arranged to penetrate outward from the inner space of the skirt support 23, such fixing bolt 140 is shown in detail in cross section in Figure 7, the head portion 142 is the It is disposed in the inner space of the skirt support 23 is disposed so as to pass through the support plate 130, the heat insulating material 110 and the skirt support 23 sequentially from the inner space of the skirt support 23.
또한 이와 같은 고정 볼트(140)는 상기 스커트 지지대(23)를 관통한 나사부가 스커트 지지대(23)의 외측에서 와셔(144)와 너트(146)로 고정되며, 이와 같은 와셔(144)는 스커트 지지대(23)의 윤곽에 일치하는 표면을 갖도록 기계 가공된 대구경 와셔(144)로 이루어짐으로써, 고정 볼트(140)의 당김 응력을 효과적으로 분산시키고, 너트(146)에 의해서 더욱 안정적으로 고정되어지도록 한다.In addition, the fixing bolt 140 is fixed to the threaded portion penetrating the skirt support 23 with the washer 144 and the nut 146 on the outside of the skirt support 23, such a washer 144 is a skirt support It consists of a large diameter washer 144 machined to have a surface consistent with the contour of 23, thereby effectively distracting the pulling stress of the fixing bolt 140 and allowing it to be more stably fixed by the nut 146.
상기와 같이 구성된 본 발명에 따른 원자로 증기 발생기의 보온재 장착구조(100)는, 도 5에 분해도로 도시된 바와 같이, 스테이 실린더(21)의 하부면에 보온재(110)를 배치시키고, 열 차단판(120)을 보온재(110)의 하부면에 밀착시킨 다음, 다수의 지지 플레이트(130)들을 열 차단판(120)의 테두리 하부면을 따라서 배치한 다음, 다수의 고정 볼트(140)들을 이용하여 스커트 지지대(23)에 고정시킨다.Insulating material mounting structure 100 of the reactor steam generator according to the present invention configured as described above, as shown in the exploded view in Figure 5, arranging the insulating material 110 on the lower surface of the stay cylinder 21, heat shielding plate After the 120 is in close contact with the lower surface of the heat insulating material 110, the plurality of supporting plates 130 are disposed along the lower surface of the edge of the heat shield plate 120, and then using a plurality of fixing bolts 140 It is fixed to the skirt support (23).
이와 같이 다수의 지지 플레이트(130)들을 이용하여 보온재(110)를 고정시키게 되면, 도 4에 도시된 바와 같이, 스테이 실린더(21)의 하부면 전체에는 보온재(110)가 열 차단판(120)에 의해서 밀착된 상태이며, 보온재(110)의 테두리(112)는 지지 플레이트(130)들에 의해서 원주방향 전체에 걸쳐서 스테이 실린더(21)와 스커트 지지대(23)의 연결부분에 견고히 고정된다. When the heat insulating material 110 is fixed using the plurality of support plates 130 as described above, as shown in FIG. 4, the heat insulating material 110 is disposed on the entire bottom surface of the stay cylinder 21. It is in close contact by the state, the edge 112 of the heat insulating material 110 is firmly fixed to the connection portion of the stay cylinder 21 and the skirt support 23 over the entire circumferential direction by the support plates 130.
또한, 지지 플레이트(130)들을 고정시킨 고정 볼트(140)들은 그 장착 방향이, 스커트 지지대(23)의 내측 공간으로부터 외측으로 관통하도록 배치되기 때문에, 시공 작업이 간편하고, 매우 용이하다.In addition, since the fixing bolts 140 fixing the support plates 130 are arranged such that their mounting direction penetrates outward from the inner space of the skirt support 23, the construction work is simple and very easy.
그리고, 스커트 지지대(23)의 외측에서는 스커트 지지대(23)의 윤곽에 일치하는 표면을 갖도록 기계 가공된 대구경 와셔(144)가 끼워짐으로써, 고정 볼트(140)의 당김 응력을 더욱 효과적으로 분산시키고, 너트(146)에 의해서 더욱 안정적으로 고정되도록 한다.Then, the outer side of the skirt support 23 is fitted with a large diameter washer 144 machined to have a surface matching the contour of the skirt support 23, thereby more effectively dispersing the pull stress of the fixing bolt 140, The nut 146 is to be more stably fixed.
이와 같이 본 발명에 의하면, 증기 발생기(9)의 스테이 실린더(21) 하부면에 보온재(110)가 완벽하게 밀착 고정된 상태이기 때문에, 원자로(1)의 운전중에 발생하는 진동에 의해서도 보온재(110)의 국부적인 처짐을 완벽하게 방지할 수 있다. As described above, according to the present invention, since the heat insulating material 110 is tightly fixed to the lower surface of the stay cylinder 21 of the steam generator 9, the heat insulating material 110 is also caused by vibration generated during operation of the reactor 1. The local sag of) can be completely prevented.
따라서, 증기 발생기(9)에서 발생된 대략 300℃의 고열이 스테이 실린더(21) 하부의 공기 정체 구역(stagnated air area)으로 복사 전달되는 것을 효과적으로 차단시킬 수 있어서, 슬라이딩 베이스(30)의 가열을 방지하고, 결과적으로 슬라이딩 베이스(30)의 열팽창 변형을 최소화시킬 수 있으며, 원자로(1) 설비의 진동 최소화에 따른 안정적인 가동이 가능한 우수한 효과를 얻을 수 있다. Thus, the high heat of approximately 300 ° C. generated in the steam generator 9 can be effectively prevented from radiating transfer to the stagnated air area under the stay cylinder 21, thereby preventing heating of the sliding base 30. It is possible to minimize the thermal expansion deformation of the sliding base 30 as a result, and to achieve an excellent effect that can be stably operated by minimizing vibration of the reactor 1 facility.
본 발명은 상기에서 도면을 참조하여 특정 실시 예에 관련하여 상세히 설명하였지만 본 발명은 이와 같은 특정 구조에 한정되는 것은 아니다. 당 업계의 통상의 지식을 가진 자라면 이하의 특허청구범위에 기재된 본 발명의 기술 사상 및 권리범위를 벗어나지 않고서도 본 발명을 다양하게 수정 또는 변경시킬 수 있을 것이다. 예를 들면, 지지 플레이트(130)들은 4개의 구조가 아닌 다수의 조각편 형태, 2~3 또는 5 이상의 형태로, 스테이 실린더(21)와 스커트 지지대(23)의 연결 부분이 형성하는 원주를 따라서 배치되는 구조일 수 있을 것이다. 또한, 고정 볼트(140)들도 다양한 배치 간격을 통해서 지지 플레이트(130)들을 고정시킬 수 있음은 물론이다. 뿐만 아니라, 열 차단판(120)은 1층의 원판 구조가 설명되었지만, 다수 겹, 또는 다수 층의 판형 구조로 이루어질 수 있음은 물론이다. 또한, 열 차단판을 슬라이딩베이스 표면에 설치하여 슬라이딩 베이스로 복사열이 전달되는 것을 미연에 방지할 수도 있다. 그렇지만 그와 같은 단순한 설계적인 수정 또는 변형 구조들은 모두 명백하게 본 발명의 권리범위 내에 속하게 됨을 미리 밝혀 두고자 한다.Although the present invention has been described in detail with reference to the accompanying drawings, the present invention is not limited to such a specific structure. Those skilled in the art may variously modify or change the present invention without departing from the spirit and scope of the present invention as set forth in the claims below. For example, the support plates 130 may be arranged along a circumference formed by the connecting portion of the stay cylinder 21 and the skirt support 23 in the form of a plurality of pieces, not more than four pieces, or two or three or five or more shapes. It may be a structure that becomes. In addition, the fixing bolts 140 may also fix the support plates 130 through various arrangement intervals. In addition, although the heat shield plate 120 has been described with a single layer disc structure, it is a matter of course that the heat shield plate 120 may be formed of a plurality of layers or a plate layer structure of multiple layers. In addition, a heat shield plate may be installed on the sliding base surface to prevent radiant heat from being transferred to the sliding base. Nevertheless, such simple design modifications or variations will be made clear in advance that all obviously fall within the scope of the present invention.
[규칙 제26조에 의한 보정 20.01.2016] 
[Revision 20.01.2016 under Rule 26]
[규칙 제26조에 의한 보정 20.01.2016] 
[Revision 20.01.2016 under Rule 26]

Claims (7)

  1. 원자로(1)에 구비된 증기 발생기로부터 전달되는 고열을 차단하여, 하부측 슬라이딩 베이스의 열변형을 방지하기 위한 보온재 장착구조에 있어서,In the thermal insulation material mounting structure for blocking the high heat transmitted from the steam generator provided in the reactor 1, to prevent thermal deformation of the lower side sliding base,
    증기 발생기의 스테이 실린더 하부면과 스커트 지지대의 내측 상부면을 따라서 배치되는 보온재; 및A heat insulating material disposed along the bottom surface of the stay cylinder of the steam generator and the inner top surface of the skirt support; And
    상기 스테이 실린더와 스커트 지지대의 연결 부분을 따라서 배치되고, 상기 스커트 지지대의 내측 공간으로부터 외측으로 관통하는 다수의 고정 볼트들을 구비하여 스테이 실린더의 하부면에 보온재를 밀착 고정시키는 지지 플레이트;를 포함하여 원자로(1)의 운전중 진동에 따른 보온재의 처짐을 방지하도록 구성되고, And a support plate disposed along a connection portion of the stay cylinder and the skirt support, and having a plurality of fixing bolts penetrating outwardly from the inner space of the skirt support to tightly fix the insulation to the bottom surface of the stay cylinder. (1) is configured to prevent sagging of the thermal insulation material due to vibration during operation,
    상기 지지 플레이트는 다수의 조각편으로 이루어지고, 상기 지지 플레이트는 상기 스테이 실린더와 스커트 지지대의 연결 부분을 따르는 원호형 구조로 이루어진 것임을 특징으로 하는 증기 발생기의 보온재 장착구조. The support plate is composed of a plurality of pieces, the support plate is a heat generator mounting structure of the steam generator, characterized in that consisting of an arcuate structure along the connecting portion of the stay cylinder and the skirt support.
  2. 제1항에 있어서, 상기 스테이 실린더와 스커트 지지대의 연결 부분이 형성하는 원주에 대해, 90도의 원주각도를 구비하며, 4개가 상기 원주 전체에 배치되어 보온재의 테두리 전체를 따라서 고정된 것임을 특징으로 하는 증기 발생기의 보온재 장착구조.The circumference of the circumference formed by the connecting portion of the stay cylinder and the skirt support, has a circumferential angle of 90 degrees, four are arranged throughout the circumference and fixed along the entire rim of the thermal insulation material Insulation structure of steam generator.
  3. 제1항에 있어서, 상기 지지 플레이트는 상기 스테이 실린더와 스커트 지지대의 연결 부분이 형성하는 윤곽에 일치하는 만곡형 단면 구조로 기계 가공되어 제작되고, 상기 스테이 실린더와 스커트 지지대의 연결 부분이 형성하는 원주에 대해, 30도의 원주 각도로 볼트 공이 형성되어 고정 볼트가 장착된 것임을 특징으로 하는 증기 발생기의 보온재 장착구조.2. The circumference of claim 1, wherein the support plate is machined and manufactured in a curved cross-sectional structure corresponding to the contour formed by the connection portion of the stay cylinder and the skirt support, and the circumference formed by the connection portion of the stay cylinder and the skirt support. And a bolt ball is formed at a circumferential angle of 30 degrees, so that the fixing bolt is mounted.
  4. 제3항에 있어서, 상기 고정 볼트는 그 머리부가 상기 스커트 지지대의 내측 공간에 배치되어 상기 스커트 지지대의 내측 공간으로부터 지지 플레이트, 보온재 및 스커트 지지대를 외측으로 관통하도록 배치되고, 상기 스커트 지지대를 관통한 나사부는 스커트 지지대의 외측에서 스커트 지지대의 윤곽에 일치하는 표면을 갖도록 기계 가공된 대구경 와셔가 끼워지고, 너트로 각각 고정된 것임을 특징으로 하는 증기 발생기의 보온재 장착구조.4. The fixing bolt of claim 3, wherein the fixing bolt is disposed in the inner space of the skirt support so as to penetrate the support plate, the insulation and the skirt support outward from the inner space of the skirt support. The screw portion is fitted with a large diameter washer machined to have a surface coincident with the contour of the skirt support on the outside of the skirt support, and is fixed with a nut, respectively.
  5. 제1항 내지 제4항 중의 어느 한 항에 있어서, 상기 보온재는 그 하부면 전체에 밀착하도록 배치된 열 차단판을 추가적으로 구비하고, 상기 열 차단판은 보온재와 지지 플레이트 사이에서 고정 볼트로 고정되어 상기 보온재를 스테이 실린더의 하부면에 밀착시키는 것임을 특징으로 하는 증기 발생기의 보온재 장착구조.The heat insulating material according to any one of claims 1 to 4, wherein the heat insulating material is further provided with a heat shielding plate arranged to be in close contact with the entire lower surface thereof, and the heat blocking plate is fixed with a fixing bolt between the heat insulating material and the support plate. Insulation material mounting structure of the steam generator, characterized in that to close contact with the heat insulating material to the lower surface of the stay cylinder.
  6. 제5항에 있어서, 상기 열 차단판은 그 테두리가 상기 스테이 실린더와 스커트 지지대의 연결 부분이 형성하는 윤곽에 일치하는 만곡형 단면의 테두리로 형성되어 지지 플레이트와의 결합시, 그 결합 표면이 상호 일치하여 밀착 결합되는 것임을 특징으로 하는 증기 발생기의 보온재 장착구조.6. The heat shielding plate according to claim 5, wherein the heat shield plate is formed with a curved cross section of edges whose edges coincide with the contours formed by the connecting portion of the stay cylinder and the skirt support, and the joining surfaces of the heat shield plates are mutually connected. Heat insulation material mounting structure of the steam generator, characterized in that the tightly coupled.
  7. 제1항 내지 제4항 중의 어느 한 항에 있어서, 상기 슬라이딩 베이스의 표면에 밀착되게 배치된 열 차단판을 더 구비하여, 슬라이딩 베이스로 복사열이 전달되는 것을 방지하도록 구성된 것임을 특징으로 하는 증기 발생기의 보온재 장착구조. The steam generator according to any one of claims 1 to 4, further comprising a heat shield plate disposed in close contact with the surface of the sliding base to prevent radiant heat from being transferred to the sliding base. Thermal insulation material mounting structure.
PCT/KR2015/013370 2015-01-29 2015-12-08 Heat insulating material mounting structure of steam generator of two-loop type pressurized light water reactor WO2016122104A1 (en)

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Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH08262176A (en) * 1995-03-17 1996-10-11 Ishikawajima Harima Heavy Ind Co Ltd Method for installing heat insulation layer of reactor pressure vessel
JPH08297189A (en) * 1995-04-26 1996-11-12 Ishikawajima Harima Heavy Ind Co Ltd Heat insulating material for reactor pressure vessel support skirt
JPH10311891A (en) * 1997-05-13 1998-11-24 Ishikawajima Harima Heavy Ind Co Ltd Cooler for reactor pressure vessel support skirt foundation
KR200167979Y1 (en) * 1999-08-09 2000-02-15 삼성중공업주식회사 Reinforcement beam structure for supporting the inner thermal insulating material of the heat recovery steam generetor
JP2002116279A (en) * 2000-10-04 2002-04-19 Babcock Hitachi Kk High-temperature vessel

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH08262176A (en) * 1995-03-17 1996-10-11 Ishikawajima Harima Heavy Ind Co Ltd Method for installing heat insulation layer of reactor pressure vessel
JPH08297189A (en) * 1995-04-26 1996-11-12 Ishikawajima Harima Heavy Ind Co Ltd Heat insulating material for reactor pressure vessel support skirt
JPH10311891A (en) * 1997-05-13 1998-11-24 Ishikawajima Harima Heavy Ind Co Ltd Cooler for reactor pressure vessel support skirt foundation
KR200167979Y1 (en) * 1999-08-09 2000-02-15 삼성중공업주식회사 Reinforcement beam structure for supporting the inner thermal insulating material of the heat recovery steam generetor
JP2002116279A (en) * 2000-10-04 2002-04-19 Babcock Hitachi Kk High-temperature vessel

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