JPH08297189A - Heat insulating material for reactor pressure vessel support skirt - Google Patents
Heat insulating material for reactor pressure vessel support skirtInfo
- Publication number
- JPH08297189A JPH08297189A JP7102342A JP10234295A JPH08297189A JP H08297189 A JPH08297189 A JP H08297189A JP 7102342 A JP7102342 A JP 7102342A JP 10234295 A JP10234295 A JP 10234295A JP H08297189 A JPH08297189 A JP H08297189A
- Authority
- JP
- Japan
- Prior art keywords
- insulating material
- heat insulating
- pressure vessel
- material portion
- reactor pressure
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【0001】[0001]
【産業上の利用分野】本発明は、原子炉圧力容器支持ス
カートの保温材に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a heat insulating material for a reactor pressure vessel support skirt.
【0002】[0002]
【従来の技術】従来の原子炉圧力容器支持スカートとそ
の保温材は、たとえば、図3に示すような構成からなっ
ている。図3において、21は原子炉圧力容器、22は
支持スカート、23はその保温材、24は後述する検査
用装置の作動範囲、25は前記圧力容器21と支持スカ
ート22の溶接部、26は検査用ポールトラックであ
る。2. Description of the Related Art A conventional reactor pressure vessel support skirt and its heat insulating material are constructed as shown in FIG. In FIG. 3, 21 is a reactor pressure vessel, 22 is a support skirt, 23 is a heat insulating material, 24 is an operating range of an inspection device described later, 25 is a welded portion between the pressure vessel 21 and the support skirt 22, and 26 is an inspection. For pole truck.
【0003】すなわち、原子炉圧力容器21の炉内熱を
外部に逃がさないために保温材23が設けられている。
そして、原子炉圧力容器21と支持スカート22は溶接
部25で溶接されているので、溶接部25については、
定期検査などが必要であり、これらの検査のとき、検査
用装置が破線で囲まれた前記作動範囲24を通過する。That is, a heat insulating material 23 is provided to prevent the heat inside the reactor of the reactor pressure vessel 21 from escaping to the outside.
Since the reactor pressure vessel 21 and the support skirt 22 are welded at the welded portion 25,
Periodic inspection and the like are required, and at the time of these inspections, the inspection device passes through the operating range 24 surrounded by a broken line.
【0004】このように、前記検査用装置が作動する場
合には、保温材23のうちの該作動範囲24に位置する
保温材部分23aとが前記検査装置と干渉するので、こ
れを避けるため、従来は上記検査中には保温材23によ
る保温を必要としないことからして、バックルなどによ
る取外し可能な構造にしたりしていた。As described above, when the inspection device is operated, the heat insulating material portion 23a of the heat insulating material 23 located in the operating range 24 interferes with the inspection device. Conventionally, since the heat insulation by the heat insulation material 23 is not required during the above-mentioned inspection, a detachable structure such as a buckle has been used.
【0005】[0005]
【発明が解決しようとする課題】しかしながら、前述し
た従来の原子炉圧力容器支持スカートの保温材は、前記
作動範囲24に位置する保温材部分23aを取外し可能
な構造にしなければならないので、その構造が複雑にな
るばかりでなく、検査時に取外し工程を必要とし、しか
も、取外した保温材部分23aの仮置きをする広いスペ
ースを必要とし、さらに、原子炉圧力容器の運転開始に
際しては前記保温材部分23aの取付け工程を必要と
し、能率的でないという問題点があった。However, the heat insulating material of the conventional reactor pressure vessel support skirt described above must have a structure in which the heat insulating material portion 23a located in the operating range 24 can be removed. Not only becomes complicated, but also requires a removal step at the time of inspection, and also requires a wide space for temporarily placing the removed heat insulating material portion 23a. Furthermore, when starting the operation of the reactor pressure vessel, the heat insulating material portion There is a problem that the step of attaching 23a is required and it is not efficient.
【0006】本発明は、上記のような問題点を解決しよ
うとするものである。すなわち、本発明は、構造が簡単
であって、かつ、検査装置との干渉が確実に避けられ、
保温材部分の取外しと取付け工程の必要がなく、仮置き
する広いスペースも必要としない原子炉圧力容器支持ス
カートの保温材を提供することを目的とするものであ
る。The present invention is intended to solve the above problems. That is, the present invention has a simple structure, and interference with the inspection device is surely avoided,
It is an object of the present invention to provide a heat retaining material for a reactor pressure vessel supporting skirt that does not require the steps of removing and attaching the heat retaining material and does not require a wide space for temporary placement.
【0007】[0007]
【課題を解決するための手段】上記目的を達成するため
に、本発明は、原子炉圧力容器の外側に位置している支
持スカートに接近して設けられた保温材において、検査
用装置の作動範囲に位置する保温材部分が、その作動範
囲より外方へ移行待避可能に設けられているものとし
た。SUMMARY OF THE INVENTION To achieve the above object, the present invention is directed to the operation of an inspection device in a heat insulator provided close to a support skirt located outside the reactor pressure vessel. It is assumed that the heat insulating material portion located in the range is provided so as to be able to move out of the operating range and be saved.
【0008】[0008]
【作用】本発明によれば、原子炉圧力容器の外側に位置
している支持スカートに接近して設けられた保温材にお
いて、検査用装置の作動範囲に位置する保温材部分が、
その作動範囲より外方へ移行待避可能に設けられている
ので、定期検査時などには、その保温材部分を単純に外
方へ移行させて検査装置との干渉を回避することがで
き、またその検査後に原子炉圧力容器の運転に際して
は、該保温材部分を単純にもとの位置へ戻して保温用と
して支障のないようにして使用することができる。According to the present invention, in the heat insulating material provided close to the support skirt located outside the reactor pressure vessel, the heat insulating material portion located in the operating range of the inspection device is
Since it is provided so that it can be moved to the outside of the operating range and saved, it is possible to avoid the interference with the inspection device by simply moving the heat insulating material part to the outside during periodic inspections. When the reactor pressure vessel is operated after the inspection, the heat insulating material portion can be simply returned to the original position and used as a heat insulating material without any trouble.
【0009】[0009]
【実施例】図1は本発明の第1実施例を示した一部切欠
縦断正面図である。図1において、1は原子炉圧力容
器、2は該容器1の外側に位置している支持スカート、
3は該スカート2に接近して設けられた保温材、4は検
査用装置の作動範囲、5は溶接部、6は検査用ポールト
ラック、7は後述する滑車、8は吊下げワイヤロープで
ある。また3aは前記保温材3のうちの該作動範囲4に
位置している保温材部分で、保温材3の全体が上下動可
能に設けられていてもよいが、この実施例では前記保温
材部分3aが矢印9で示すように、部分的に上下動可能
に設けられている。すなわち、保温材部分3aには滑車
7が取付けられていて、該滑車7が図示されていないク
レーンから吊下げられた前記ワイヤロープ8と係合して
いる。DESCRIPTION OF THE PREFERRED EMBODIMENTS FIG. 1 is a partially cutaway vertical front view showing a first embodiment of the present invention. In FIG. 1, 1 is a reactor pressure vessel, 2 is a support skirt located outside the vessel 1,
3 is a heat insulating material provided close to the skirt 2, 4 is an operating range of the inspection device, 5 is a welding portion, 6 is an inspection pole track, 7 is a pulley to be described later, and 8 is a hanging wire rope. . Reference numeral 3a denotes a heat insulating material portion of the heat insulating material 3 located in the operating range 4, and the whole heat insulating material 3 may be provided so as to be vertically movable. In this embodiment, the heat insulating material portion is provided. 3a is provided so as to be partially movable up and down, as indicated by an arrow 9. That is, a pulley 7 is attached to the heat insulating material portion 3a, and the pulley 7 is engaged with the wire rope 8 suspended from a crane (not shown).
【0010】図1に示すように構成された原子炉圧力容
器支持スカートの保温材においては、定期検査時などに
は、前記保温材部分3aを二点鎖線で示すように、上方
へ移行させておくことで、検査装置との干渉を回避する
とができる。またその検査後に原子炉圧力容器1の運転
に際しては、該保温材部分3aを実線で示すように下降
させてもとの位置に戻し、保温用として支障のないよう
にして使用する。In the heat insulating material of the reactor pressure vessel support skirt constructed as shown in FIG. 1, the heat insulating material portion 3a is moved upward as shown by a chain double-dashed line at the time of periodic inspection. By setting it, it is possible to avoid interference with the inspection device. Further, after the inspection, when the reactor pressure vessel 1 is operated, the heat insulating material portion 3a is returned to the original position as shown by the solid line so that the heat insulating material portion 3a is used for heat insulation without any trouble.
【0011】なお図1に示した実施例では、保温材部分
3aを上方へ移行待避させる手段として、滑車7とワイ
ヤロープ8による手段を述べたが、その他、作業員の手
作業によってもよく、あるいは前記作動範囲4に支障の
ない位置にジャッキを据付けて行なってもよい。In the embodiment shown in FIG. 1, the pulley 7 and the wire rope 8 are used as means for shifting and retracting the heat insulating material portion 3a. However, it may be manually operated by an operator. Alternatively, the jack may be installed at a position that does not interfere with the operation range 4.
【0012】図2は本発明の第2実施例を示した一部切
欠縦断正面図である。図2において、符号1ないし5は
図1の場合と同じである。また3aも図1の場合と同じ
である。そして保温材3は作動範囲4に位置する保温材
部分3aと、これより上位の保温材部分3bとからなっ
ており、これら保温材部分3a,3bは蝶番10で結合
されている。すなわち、前記作動範囲4に位置する保温
材部分3aがこれより上位の保温材部分3bに対して矢
印11で示すように開閉可能に蝶番10で結合されてい
る。FIG. 2 is a partially cutaway vertical front view showing a second embodiment of the present invention. In FIG. 2, reference numerals 1 to 5 are the same as those in FIG. Also, 3a is the same as in the case of FIG. The heat insulating material 3 is composed of a heat insulating material portion 3a located in the operating range 4 and a heat insulating material portion 3b higher than the heat insulating material portion 3a, and these heat insulating material portions 3a and 3b are connected by a hinge 10. That is, the heat insulating material portion 3a located in the operating range 4 is connected to the heat insulating material portion 3b higher than the heat insulating material portion 3a by the hinge 10 so as to be openable and closable as shown by an arrow 11.
【0013】図2に示すように構成された原子炉圧力容
器支持スカートの保温材においては、定期検査時などに
は、保温材部分3aを二点鎖線で示すように、前記作動
範囲4から外方へ開いておくことで、検査装置との干渉
を回避することができる。またその検査後に原子炉圧力
容器1の運転に際しては、該保温部材3aを実線で示す
ように閉にしてもとの位置に戻し、保温用として支障の
ないようにして使用する。In the heat insulating material of the reactor pressure vessel supporting skirt constructed as shown in FIG. 2, the heat insulating material portion 3a is outside the operating range 4 as shown by a chain double-dashed line at the time of periodic inspection. By opening to one side, interference with the inspection device can be avoided. When the reactor pressure vessel 1 is operated after the inspection, the heat retaining member 3a is returned to its original position even if it is closed as shown by the solid line so that the heat retaining member 3a is used for heat retention without any trouble.
【0014】なお該保温材部分3aの平面図を省略して
いるが、平面図でいえば、扇形になっていて、該保温材
部分3aの前述の開閉は格別な駆動装置を必要とするこ
となく、作業員の手動操作でできるようになっている。
また該保温材部分3aの開閉後の係止手段については、
二点鎖線で示す開の状態では、該部分3aの自重によっ
てその位置を保持しているが、実線の閉の状態では蝶番
10に対する自重のモーメントが作用するので、該圧力
容器1の外面と該保温材部分3aの両方に係合部材を設
けてそれらを係合させて係止するようにする。Although a plan view of the heat insulating material portion 3a is omitted, the heat insulating material portion 3a has a fan shape in plan view, and the opening and closing of the heat insulating material portion 3a requires a special drive device. Instead, it can be done manually by a worker.
Regarding the locking means after opening and closing the heat insulating material portion 3a,
In the open state shown by the chain double-dashed line, its position is held by the weight of the portion 3a, but in the closed state of the solid line, the moment of its own weight with respect to the hinge 10 acts, so Engagement members are provided on both of the heat insulating material portions 3a to engage and lock them.
【0015】[0015]
【発明の効果】以上説明したように、本発明によれば、
原子炉圧力容器の外側に位置している支持スカートに接
近して設けられた保温材において、検査用装置の作動範
囲に位置する保温材部分が、その作動範囲より外方へ移
行待避可能に設けられているので、定期検査時などに
は、その保温材部分を単純に外方へ移行させて検査装置
との干渉を回避することができ、またその検査後に原子
炉圧力容器の運転に際しては該保温材部分を単純にもと
の位置へ戻して保温用として支障のないようにして使用
することができる。As described above, according to the present invention,
In the heat insulating material provided close to the support skirt located outside the reactor pressure vessel, the heat insulating material portion located in the operating range of the inspection device is provided so that it can be moved to the outside of the operating range and retracted. Therefore, at the time of periodic inspection, it is possible to simply move the heat insulating material part to the outside to avoid interference with the inspection device, and when operating the reactor pressure vessel after the inspection, The heat insulating material portion can be simply returned to the original position and used as a heat insulating material without any trouble.
【0016】このように、本発明によれば、バックルな
どを使用することなく、構造が簡単であって、かつ、保
温材部分の取外しと取付け工程の必要がなく、仮置きす
るための広いスペースを必要としないばかりでなく、該
保温材部分の移行させた後の保温材まわりのスペースの
有効利用を図ることができる。As described above, according to the present invention, a buckle or the like is not used, the structure is simple, and there is no need to remove and attach the heat insulating material portion, and a wide space for temporary placement is provided. Not only is it unnecessary, but also the space around the heat insulating material after the heat insulating material is transferred can be effectively used.
【図1】本発明の第1実施例を示した一部切欠縦断正面
図である。FIG. 1 is a partially cutaway vertical front view showing a first embodiment of the present invention.
【図2】本発明の第2実施例を示した一部切欠縦断正面
図である。FIG. 2 is a partially cutaway vertical front view showing a second embodiment of the present invention.
【図3】従来の技術の一例を示した一部切欠縦断正面図
である。FIG. 3 is a partially cutaway vertical front view showing an example of a conventional technique.
1 原子炉圧力容器 2 支持スカート 3 保温材 3a 保温材部分 3b 上位の保温材部分 4 作動範囲 5 溶接部 6 検査用ポールトラック 10 蝶番 1 Reactor Pressure Vessel 2 Support Skirt 3 Heat Insulating Material 3a Heat Insulating Material Part 3b Upper Heat Insulating Material Part 4 Operating Range 5 Welding Part 6 Inspection Pole Track 10 Hinge
Claims (3)
持スカートに接近して設けられた保温材において、検査
用装置の作動範囲に位置する保温材部分が、その作動範
囲より外方へ移行待避可能に設けられていることを特徴
とする、原子炉圧力容器支持スカートの保温材。1. A heat insulating material provided close to a support skirt located outside a reactor pressure vessel, wherein the heat insulating material portion located in the operating range of the inspection device is located outside the operating range. A heat insulating material for a reactor pressure vessel support skirt, which is provided so as to be able to save transition.
温材部分が、その作動範囲より上方へ移行待避可能に設
けられている請求項1記載の原子炉圧力容器支持スカー
トの保温材。2. The heat insulating material for a reactor pressure vessel support skirt according to claim 1, wherein the heat insulating material portion located in the operating range of the inspection device is provided so as to be able to move upward from the operating range and to be saved.
温材部分が、これより上位の保温材部分に対して開閉可
能に蝶番で結合されている請求項1記載の原子炉圧力容
器支持スカートの保温材。3. The reactor pressure vessel support skirt according to claim 1, wherein the heat insulating material portion located in the operating range of the inspection device is hinged to the heat insulating material portion above it so as to be openable and closable. Insulation material.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP7102342A JPH08297189A (en) | 1995-04-26 | 1995-04-26 | Heat insulating material for reactor pressure vessel support skirt |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP7102342A JPH08297189A (en) | 1995-04-26 | 1995-04-26 | Heat insulating material for reactor pressure vessel support skirt |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH08297189A true JPH08297189A (en) | 1996-11-12 |
Family
ID=14324830
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP7102342A Pending JPH08297189A (en) | 1995-04-26 | 1995-04-26 | Heat insulating material for reactor pressure vessel support skirt |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH08297189A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2016122104A1 (en) * | 2015-01-29 | 2016-08-04 | 문인득 | Heat insulating material mounting structure of steam generator of two-loop type pressurized light water reactor |
-
1995
- 1995-04-26 JP JP7102342A patent/JPH08297189A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2016122104A1 (en) * | 2015-01-29 | 2016-08-04 | 문인득 | Heat insulating material mounting structure of steam generator of two-loop type pressurized light water reactor |
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