JP3132983B2 - Cavity seal for reactor vessel and method of manufacturing the same - Google Patents
Cavity seal for reactor vessel and method of manufacturing the sameInfo
- Publication number
- JP3132983B2 JP3132983B2 JP07166311A JP16631195A JP3132983B2 JP 3132983 B2 JP3132983 B2 JP 3132983B2 JP 07166311 A JP07166311 A JP 07166311A JP 16631195 A JP16631195 A JP 16631195A JP 3132983 B2 JP3132983 B2 JP 3132983B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor vessel
- cavity
- cavity seal
- cylindrical
- reactor
- 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.)
- Expired - Lifetime
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
- Butt Welding And Welding Of Specific Article (AREA)
Description
【0001】[0001]
【産業上の利用分野】本発明は、原子炉格納容器内の構
造に関し、特に原子炉容器用キャビティシールの構造に
関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a structure inside a containment vessel, and more particularly to a structure of a cavity seal for a reactor vessel.
【0002】[0002]
【従来の技術】従来、軽水冷却型原子炉においては、図
4に示すように原子炉容器1は、図示しない原子炉格納
容器内のコンクリート構造物3(内部に鉄骨等を含む)
に形成された原子炉キャビティ5の中に垂下する様に据
え付けられる。その原子炉キャビティ5には、燃料交換
時に遮蔽水が張られ、原子炉容器1内の核燃料は、その
遮蔽水中を移送される。従って、原子炉容器1が入って
いるウェル乃至穴内に遮蔽水が入り込まないようにキャ
ビティシール7が用いられる。キャビティシール7は、
燃料交換時のみ設ければ一応用が足りるが、取付け取外
しの煩雑さや放射能汚染等の問題もあり、恒設(常時設
けておくこと)される場合が多い。2. Description of the Related Art Conventionally, in a light water-cooled reactor, as shown in FIG. 4, a reactor vessel 1 is a concrete structure 3 (including a steel frame and the like inside) in a containment vessel (not shown).
Is installed so as to hang down in the reactor cavity 5 formed in the above. The reactor cavity 5 is filled with shield water during refueling, and nuclear fuel in the reactor vessel 1 is transferred through the shield water. Therefore, the cavity seal 7 is used so that shielding water does not enter the well or the hole in which the reactor vessel 1 is contained. The cavity seal 7
One application is sufficient if it is provided only at the time of refueling, but it is often fixed (it is always provided) due to problems such as complicated installation and removal and radioactive contamination.
【0003】図5に、前述の従来型キャビティシール7
の詳細構造が拡大断面図として示されている。原子炉容
器1は、その出力により大きさは変わるが、一般に数メ
ートルの直径を有するから、原子炉容器本体1aのフラ
ンジの外周部に取り付けられるキャビティシール7は、
相当に大きな円環状構造物であり、取り合いリング7
a,7bと、円筒状のシールプレート7cとからなる。
取り合いリング7a,7bは、それぞれ容器本体1aと
原子炉キャビティ5に対する結合部材の機能をもってい
る。そして、シールプレート7cは、図6に示すように
多数の板材を溶接接合により組み立てて形成されてい
る。尚、原子炉容器本体1aは、保温材8で囲まれ、冷
却空気9は、矢印に示すように流れている。FIG. 5 shows a conventional cavity seal 7 described above.
Is shown as an enlarged sectional view. Although the size of the reactor vessel 1 varies depending on its output, it generally has a diameter of several meters. Therefore, the cavity seal 7 attached to the outer peripheral portion of the flange of the reactor vessel body 1a
It is a considerably large annular structure, and the connecting ring 7
a, 7b and a cylindrical seal plate 7c.
The connecting rings 7a and 7b function as connecting members for the vessel main body 1a and the reactor cavity 5, respectively. The seal plate 7c is formed by assembling a large number of plate members by welding as shown in FIG. The reactor vessel main body 1a is surrounded by a heat insulating material 8, and the cooling air 9 flows as shown by an arrow.
【0004】[0004]
【発明が解決しようとする課題】而して、外部空気や冷
却空気に晒されているコンクリート構造物3は、原子炉
運転中も比較的低温に保持されるのに対し、原子炉容器
1特にその上部は運転中相当の高温に達し、熱膨張量も
大きくなる。従って、両者の間に相対変位が生ずる。こ
の相対変位は、両者の間にあるキャビティシール7の変
形によって吸収される。これらの状況を図7を参照して
説明すると、(a)は、原子炉運転休止中(製作時を含
む)の状態を示し、原子炉が運転されると(b)に示す
ような状態となる。即ち、原子炉容器本体1aのフラン
ジと共に膨張する傾向をもつ取り合いリング7bと、コ
ンクリート構造物3に拘束される取り合いリング7aと
同一挙動を取るシールプレート7cとの接合部に変形が
集中し、この部分に高応力が発生しやすい。これは、原
子炉出力の増大傾向に伴って原子炉容器1も大きくなる
ので、増大傾向にある。また、シールプレート7cが大
形化すると、使用板材片の数も増し、溶接線も増える。
とかく溶接部は、他の部位に比して相対的に材料欠陥が
生じやすい部位であるので、確率的にはここに熱変形が
集中すると熱疲労破壊が生じやすい。本発明は、如上の
事情に鑑みなされれたもので、溶接線が少なく、かつ溶
接部に熱変形が集中しない原子炉容器キャビティシール
及びその製作方法を提供することを目的とする。The concrete structure 3 exposed to the outside air or the cooling air is kept at a relatively low temperature during the operation of the reactor, whereas the concrete structure 3 is kept at a relatively low temperature. The upper part reaches a considerably high temperature during operation, and the amount of thermal expansion also increases. Therefore, a relative displacement occurs between the two. This relative displacement is absorbed by the deformation of the cavity seal 7 between them. These situations will be described with reference to FIG. 7. FIG. 7A shows a state in which the reactor operation is suspended (including the time of manufacture), and when the reactor is operated, the state shown in FIG. Become. That is, the deformation concentrates on the joint between the joint ring 7b that tends to expand together with the flange of the reactor vessel main body 1a and the seal plate 7c that behaves the same as the joint ring 7a restrained by the concrete structure 3. High stress is likely to occur in the part. This is because the reactor vessel 1 also becomes larger in accordance with the tendency of the reactor power to increase. Further, when the size of the seal plate 7c is increased, the number of used plate materials increases, and the number of welding lines also increases.
Anyway, since the welded portion is a portion where material defects are relatively likely to occur as compared with other portions, stochastically, if thermal deformation is concentrated here, thermal fatigue fracture is likely to occur. The present invention has been made in view of the above circumstances, and an object of the present invention is to provide a reactor vessel cavity seal in which the number of welding lines is small and thermal deformation is not concentrated on a weld portion, and a method of manufacturing the same.
【0005】[0005]
【課題を解決するための手段】如上の目的を達成するた
め、本発明によれば、コンクリート構造物により形成さ
れた原子炉キャビティの底面と、同底面の穴内に垂下支
持される原子炉容器との間を閉じるキャビティシール
は、原子炉キャビティの底面に接合される下部円板部
と、中間の円筒部と、原子炉容器に接合される上部リン
グ部とが互いに溶接されて形成され、前記円筒部の下端
部に半径方向内方に突出する湾状断面部を形成したこと
を特徴とする。また、本発明方法によれば、前述のキャ
ビティシールの円筒部は、帯板材料を円筒形に曲げ加工
し、前記帯板材料の両端部を溶接接合して円筒状ブラン
クとし、同円筒状ブランクの適所にロール成形により円
周方向に延びるベローズ構造を形成し、しかる後前記ベ
ローズ構造の外端部を円周状に切断する工程を経て製作
され、これが下部円板部と上部リング部とにそれぞれ溶
接されてキャビティシールが最終的に製作される。According to the present invention, there is provided, in accordance with the present invention, a bottom surface of a reactor cavity formed by a concrete structure, and a reactor vessel suspended and supported in a hole in the bottom surface. The cavity seal that closes the gap is formed by welding a lower disk part joined to the bottom surface of the reactor cavity, an intermediate cylindrical part, and an upper ring part joined to the reactor vessel, and A bay-shaped cross section projecting inward in the radial direction is formed at the lower end of the section. According to the method of the present invention, the cylindrical portion of the cavity seal is formed by bending a strip material into a cylindrical shape, and welding and joining both ends of the strip material to form a cylindrical blank. A bellows structure extending in the circumferential direction is formed by roll forming in an appropriate place, and then manufactured through a process of cutting the outer end of the bellows structure in a circumferential shape, and this is formed into a lower disk portion and an upper ring portion. Each is welded to finally produce a cavity seal.
【0006】[0006]
【作用】前述の構成のキャビティシールでは、原子炉の
運転時、下部円板部が原子炉キャビティの底面に固定さ
れてこれに従動し、上部リング部は原子炉容器に固定さ
れてこれに従動し、両者の熱膨張差は円筒部の変形で吸
収される。円筒部はその下端部に湾状断面部を有してい
るから、断面的に見ると曲り梁的に変形し、変形は分散
され接合部に集中しない。又、前記した円筒部の製作で
は、軸方向溶接線は丸めた帯板の両端部間にのみ軸方向
溶接線が存在し、溶接線の数が削減される。In the cavity seal having the above-described structure, during operation of the reactor, the lower disk portion is fixed to and driven by the bottom surface of the reactor cavity, and the upper ring portion is fixed to and driven by the reactor vessel. However, the difference in thermal expansion between the two is absorbed by the deformation of the cylindrical portion. Since the cylindrical portion has a bay-shaped cross-section at its lower end, it deforms like a curved beam when viewed in cross section, and the deformation is dispersed and does not concentrate on the joint. Further, in the manufacture of the above-mentioned cylindrical portion, the axial welding line exists only between both ends of the rounded strip, and the number of welding lines is reduced.
【0007】[0007]
【実施例】以下添付の図面を参照して本発明の実施例を
説明する。尚従来の構造を説明する図面を含め、同一部
分には同一の符号を付している。図1において、原子炉
容器1の本体1aは保温材8に囲まれ、その上部フラン
ジに本発明によるキャビティシール20の上部リング部
21が溶接により接合されている。また、円筒部23を
介して上部リング部21に連結された下部円板部25
は、コンクリート構造物3の表面に設けられたライナ板
15に溶接されている。尚、キャビティシール20は、
取り付け後保護蓋16で覆われて保護される。Embodiments of the present invention will be described below with reference to the accompanying drawings. In addition, the same reference numerals are given to the same parts including the drawings for explaining the conventional structure. In FIG. 1, a main body 1a of a reactor vessel 1 is surrounded by a heat insulating material 8, and an upper ring portion 21 of a cavity seal 20 according to the present invention is joined to an upper flange thereof by welding. Also, a lower disk portion 25 connected to the upper ring portion 21 via the cylindrical portion 23
Are welded to a liner plate 15 provided on the surface of the concrete structure 3. The cavity seal 20 is
After the attachment, it is covered and protected by the protective lid 16.
【0008】図2には、キャビティシール20の構造の
詳細が示されている。容器本体1aに接合された上部リ
ング部21は、相対的に厚肉であるが薄肉の延長部21
aを有し、この延長部21aが円筒部23の上端に溶接
により接合されている。尚、延長部21aの付け根の断
面変化部は、適当な径の円弧を描いて応力集中を緩和し
ている。また、円筒部23の下部には、緩やかな変曲部
をもつ湾状断面部23aが形成され、これに下部円板部
25が溶接接合されている。更に、下部円板部25は、
従来のものと同様な取り合いリング25aを有し、ライ
ナ板15に溶接により固定されている。前述の溶接は、
いずれの場所に置いても連続溶接で隙間なく行われるの
で、キャビティシール20の外側に燃料交換用遮蔽水が
供給されても、原子炉容器1側の内側に漏れ出ることは
ない。FIG. 2 shows details of the structure of the cavity seal 20. The upper ring portion 21 joined to the container body 1a has a relatively thick but thin extension portion 21.
a, and the extended portion 21 a is joined to the upper end of the cylindrical portion 23 by welding. In addition, the cross-section changing part of the base of the extension part 21a draws an arc of an appropriate diameter to reduce stress concentration. Further, a lower portion of the cylindrical portion 23 is formed with a bay-shaped cross-sectional portion 23a having a gentle inflection portion, and the lower disk portion 25 is welded thereto. Further, the lower disk portion 25
It has an engaging ring 25a similar to the conventional one, and is fixed to the liner plate 15 by welding. The aforementioned welding is
Regardless of the location, the continuous welding is performed without any gap, so that even if the refueling shielding water is supplied to the outside of the cavity seal 20, it does not leak to the inside of the reactor vessel 1 side.
【0009】次に、上述の形状の円筒部23を製作する
手順を図3を参照して説明すると、所定の幅及び長さの
帯板材料をベンダー等で曲げて円筒形に成形し、両端部
を突き合わせ溶接して、円筒状ブランク30とする
(a)。そしてその円筒状ブランク30の所定位置をロ
ール17,19により成形してべローズ構造31を形成
する(b)。更に、ベローズ構造31の外端部を円周状
に切断し、外端部及びブランク30の下部分を除去すれ
ば、ブランク30の残った上部分が前述の円筒部23と
なり、ベローズ構造31の残部が湾状部23aとなる
(c)。このようにして製作された円筒部23は、通常
の方法により上部リング部21及び下部円板部25に溶
接接合される。Next, a procedure for manufacturing the cylindrical portion 23 having the above-described shape will be described with reference to FIG. 3. A band plate material having a predetermined width and length is bent by a bender or the like and formed into a cylindrical shape. The parts are butt-welded to form a cylindrical blank 30 (a). Then, a predetermined position of the cylindrical blank 30 is formed by the rolls 17 and 19 to form the bellows structure 31 (b). Further, if the outer end of the bellows structure 31 is cut in a circumferential shape and the outer end and the lower part of the blank 30 are removed, the remaining upper part of the blank 30 becomes the above-mentioned cylindrical portion 23, and the bellows structure 31 The remaining portion becomes the bay portion 23a (c). The cylindrical portion 23 thus manufactured is welded to the upper ring portion 21 and the lower disk portion 25 by a usual method.
【0010】下部円板部25の取り合いリング25a以
外の板状部分は、弧状板材を放射方向に延びる溶接線で
溶接接合されて製作されるのが一般である。上部リング
部21及び取り合いリング25aは、一体材料から製作
しても良いが、複数のセグメント部分を溶接接合により
組立ててもよい。The plate-shaped portion of the lower disk portion 25 other than the connecting ring 25a is generally manufactured by welding and joining an arc-shaped plate material with a welding line extending in a radial direction. The upper ring portion 21 and the connecting ring 25a may be manufactured from an integral material, or a plurality of segment portions may be assembled by welding.
【0011】以上説明したように製作され、原子炉容器
1と原子炉キャビティ5の底面との間に架設されたキャ
ビティシール20は、従来のものと同様原子炉キャビテ
ィ5に遮蔽水が張られたときその流出を防止する。原子
炉キャビティ5と原子炉容器1との間に熱膨張差による
相対変位があると、図2において上部リング部21が左
方(図において)に相対変位し、円筒部23が湾状断面
部23aの作用によりなだらかに変形して熱膨張差を吸
収する。又、上部リング部21の断面急変部に溶接部が
ないので、そこには熱応力が集中しない。The cavity seal 20 manufactured as described above and installed between the reactor vessel 1 and the bottom surface of the reactor cavity 5 has shielding water applied to the reactor cavity 5 as in the conventional case. Sometimes prevent its outflow. When there is a relative displacement between the reactor cavity 5 and the reactor vessel 1 due to a difference in thermal expansion, the upper ring portion 21 is relatively displaced to the left (in the drawing) in FIG. Due to the action of 23a, it is gently deformed to absorb the difference in thermal expansion. Further, since there is no welded portion in the suddenly changing section of the upper ring portion 21, thermal stress is not concentrated there.
【0012】[0012]
【発明の効果】以上説明したように、請求項1の発明に
よればキャビティシールの円筒部に湾状断面部を形成し
たので、熱膨張差による変形が集中せずは分散して生ず
るので発生熱応力も小さく、熱疲労破壊を防止すること
ができる。請求項2の発明によれば、円筒部を製作する
に際し、帯板材料を曲げ加工して両端を溶接するので、
溶接線が最小になり、溶接部の熱疲労破壊を防止するこ
とができる。As described above, according to the first aspect of the present invention, since the bay-shaped cross-section is formed in the cylindrical portion of the cavity seal, the deformation due to the difference in thermal expansion occurs not concentrated but occurs in a dispersed manner. Thermal stress is small, and thermal fatigue fracture can be prevented. According to the invention of claim 2, when manufacturing the cylindrical portion, since the strip material is bent and welded at both ends,
The weld line is minimized and thermal fatigue fracture of the weld can be prevented.
【図1】本発明の実施例の要部を示す部分断面図であ
る。FIG. 1 is a partial sectional view showing a main part of an embodiment of the present invention.
【図2】図1の部分拡大断面図である。FIG. 2 is a partially enlarged sectional view of FIG.
【図3】本発明の方法の手順を示す工程図である。FIG. 3 is a process chart showing the procedure of the method of the present invention.
【図4】本発明のキャビティシールが使用される状況を
示す概念図である。FIG. 4 is a conceptual diagram showing a situation in which the cavity seal of the present invention is used.
【図5】従来のものの取り付けた状態を示す部分断面図
である。FIG. 5 is a partial cross-sectional view showing a state where a conventional device is attached.
【図6】従来のものの1部分を示す斜視図である。FIG. 6 is a perspective view showing a part of a conventional device.
【図7】従来のものの不具合の状況を示す説明図であ
る。FIG. 7 is an explanatory diagram showing a state of a defect of a conventional device.
1 原子炉容器 3 コンクリート構造物 5 原子炉キャビティ 20 キャビティシール 21 上部リング部 23 円筒部 23a 湾状断面部 25 下部円板部 DESCRIPTION OF SYMBOLS 1 Reactor vessel 3 Concrete structure 5 Reactor cavity 20 Cavity seal 21 Upper ring part 23 Cylindrical part 23a Bay-like cross section 25 Lower disc part
───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭58−214886(JP,A) 特開 昭59−70997(JP,A) 実開 昭54−3600(JP,U) (58)調査した分野(Int.Cl.7,DB名) G21C 13/028 ──────────────────────────────────────────────────続 き Continuation of the front page (56) References JP-A-58-214886 (JP, A) JP-A-59-70997 (JP, A) Jikai Sho 54-3600 (JP, U) (58) Field (Int.Cl. 7 , DB name) G21C 13/028
Claims (2)
子炉キャビティの底面と、同底面の穴内に垂下支持され
る原子炉容器との間を閉じるキャビティシールであっ
て、前記原子炉キャビティの底面に接合される下部円板
部と、中間の円筒部と、前記原子炉容器に接合される上
部リング部とが互いに溶接されて構成され、前記円筒部
の下端部に半径方向内方に突出する湾状断面部を形成し
たことを特徴とする原子炉容器用キャビティシール。1. A cavity seal for closing between a bottom surface of a reactor cavity formed by a concrete structure and a reactor vessel suspended and supported in a hole in the bottom surface, the cavity seal being joined to the bottom surface of the reactor cavity. A lower disk portion, an intermediate cylindrical portion, and an upper ring portion joined to the reactor vessel are welded to each other, and are formed in a bay shape projecting radially inward at a lower end portion of the cylindrical portion. A cavity seal for a nuclear reactor vessel, wherein a cross section is formed.
板材料の両端部を溶接接合して円筒状ブランクとし、同
円筒状ブランクの適所にロール成形により円周方向に延
びたベローズ構造を形成し、しかる後前記ベローズ構造
の外端部を円周状に切断して円筒部を製作し、同円筒部
に下部円板部と上部リング部をそれぞれ溶接することを
特徴とする請求項1記載の原子炉容器用キャビティシー
ルを製作する方法。2. A bellows which is formed by bending a strip material into a cylindrical shape, welding and joining both ends of the strip material to form a cylindrical blank, and circumferentially extending by roll forming at an appropriate position of the cylindrical blank. A structure is formed, and thereafter, an outer end portion of the bellows structure is circumferentially cut to form a cylindrical portion, and a lower disk portion and an upper ring portion are welded to the cylindrical portion, respectively. Item 3. A method for producing a cavity seal for a nuclear reactor vessel according to Item 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP07166311A JP3132983B2 (en) | 1995-06-30 | 1995-06-30 | Cavity seal for reactor vessel and method of manufacturing the same |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP07166311A JP3132983B2 (en) | 1995-06-30 | 1995-06-30 | Cavity seal for reactor vessel and method of manufacturing the same |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0915369A JPH0915369A (en) | 1997-01-17 |
| JP3132983B2 true JP3132983B2 (en) | 2001-02-05 |
Family
ID=15829001
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP07166311A Expired - Lifetime JP3132983B2 (en) | 1995-06-30 | 1995-06-30 | Cavity seal for reactor vessel and method of manufacturing the same |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3132983B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116729589B (en) * | 2023-07-28 | 2025-11-18 | 广州文冲船厂有限责任公司 | Fuel tank manufacturing method and fuel tank |
-
1995
- 1995-06-30 JP JP07166311A patent/JP3132983B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0915369A (en) | 1997-01-17 |
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