JPH0126436B2 - - Google Patents
Info
- Publication number
- JPH0126436B2 JPH0126436B2 JP56101613A JP10161381A JPH0126436B2 JP H0126436 B2 JPH0126436 B2 JP H0126436B2 JP 56101613 A JP56101613 A JP 56101613A JP 10161381 A JP10161381 A JP 10161381A JP H0126436 B2 JPH0126436 B2 JP H0126436B2
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- sleeve
- reactor containment
- penetration
- pipe
- 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
Links
- 230000035515 penetration Effects 0.000 claims description 30
- 230000000149 penetrating effect Effects 0.000 claims description 20
- 239000004567 concrete Substances 0.000 claims description 10
- 230000017525 heat dissipation Effects 0.000 claims description 8
- 230000005855 radiation Effects 0.000 description 7
- 229910000831 Steel Inorganic materials 0.000 description 6
- 239000010959 steel Substances 0.000 description 6
- 230000003014 reinforcing effect Effects 0.000 description 4
- 239000011810 insulating material Substances 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 2
- 230000002093 peripheral effect Effects 0.000 description 2
- 239000011150 reinforced concrete Substances 0.000 description 2
- 230000001629 suppression Effects 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 231100000989 no adverse effect Toxicity 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000003507 refrigerant Substances 0.000 description 1
- 230000002787 reinforcement Effects 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
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
-
- 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
- Devices For Medical Bathing And Washing (AREA)
- Discharge Heating (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
［発明の目的］
（産業上の利用分野）
本発明はコンクリート製の原子炉格納容器にお
ける配管貫通装置に関する。
（従来の技術）
従来、原子炉格納容器は耐圧性と気密性を有す
る鋼製の原子炉格納容器を設け、この周囲にコン
クリート製の遮蔽壁を設け、内部で冷却材の漏洩
等が生じた場合の放射性物質の拡散を防止すると
ともに放射線の遮蔽をおこなつていた。しかし、
このようなものでは構造が複雑となり、建設コス
トが高くなる不具合があつた。そして、このよう
な鋼製の原子炉格納容器に代つて第１図および第
２図に示す如きコンクリート製の原子炉格納容器
が開発されている。すなわち、図中１は格納容器
本体であつて、鉄筋コンクリート等で強固に形成
され、耐圧性と放射線の遮蔽能力が与えられてい
る。そして、この格納容器本体１の内面には比較
的薄い鋼板からなるライナー２が密着して設けら
れ、気密性が与えられている。そして、この原子
炉格納容器内には原子炉圧力容器３が収容され、
また下部にはサプレツシヨンチヤンバ４が形成さ
れている。また、配管たとえば主蒸気配管５は配
管貫通装置６を介してこの原子炉格納容器を貫通
している。ところで、このようなコンクリート製
の原子炉格納容器は構造が簡単であるとともに原
子炉格納容器自体が充分な強度、剛性を有してい
るので配管等をこの原子炉格納容器に支持させる
ことができる長所がある。そして、従来のものは
第２図に示す如く配管貫通装置６を介して配管た
とえば主蒸気配管５をこの原子炉格納容器に支持
している。すなわち、７は貫通スリーブであつて
格納容器本体１およびライナー２を貫通して設け
られ、アンカー８…、およびアンカープレート９
により格納容器本体１に固定されている。そし
て、この貫通スリーブ７内には主蒸気配管５が間
隙をもつて挿通されている。そして、この貫通ス
リーブ７の原子炉格納容器外側（第２図では右
方）の端部には閉塞支持部材１０が設けられてお
り、この閉塞支持部材１０によつて貫通スリーブ
７と主蒸気配管５との間が気密に閉塞され、また
この主蒸気配管５が貫通スリーブ７に支持されて
いる。したがつて熱膨張等によつてこの主蒸気配
管５に生じる軸方向の荷重やねじれ荷重は上記閉
塞支持部材１０、貫通スリーブ７を介して格納容
器本体１で支持される。
（発明が解決しようとする課題）
しかし、このようなものは主蒸気配管５の荷重
が貫通スリーブ７のアンカー８…やアンカープレ
ート９によつて格納容器本体１に伝えられるの
で、この格納容器本体１にはこの部分に局部的な
荷重が作用することになる。また、この主蒸気配
管５は高温の蒸気が流通されるので、その熱が閉
塞支持部材１０を介して貫通スリーブ７に伝導さ
れ、また輻射、対流によつてもこの貫通スリーブ
７に伝えられる。このため貫通スリーブ７の温度
が上昇し、その周囲の格納容器本体１も温度が上
昇してコンクリートの強度が低下することが考え
られる。このためこの配管貫通装置６の近傍にお
ける格納容器本体１の健全性評価が厳しくなり、
この配管貫通装置６の近傍部分に特別の補強等を
施さねばならない等の不具合があつた。このた
め、従来は主蒸気配管５と貫通スリーブ６との間
に断熱材を介在させることもなされているが効果
が不充分であつた。また主蒸気配管５と貫通スリ
ーブ６との間に冷却管を設け、この冷却管に冷媒
を流通させて貫通スリーブ７の温度上昇を防止す
ることもなされているが、このようなものは構造
が複雑になる等の不具合があつた。
本発明は以上の事情にもとづいてなされたもの
で、その目的とするところはコンクリート製の原
子炉格納容器の健全性に悪影響を与えることがな
く、かつ構造が簡単な配管貫通装置を得ることに
ある。
［発明の構成］
（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、コンクリ
ート製の原子炉格納容器を貫通して設けられた貫
通スリーブと、この貫通スリーブ内を間隙をもつ
て挿通された配管と、この配管と上記貫通スリー
ブとの間隙を気密に閉塞すると共に上記配管を支
持する閉塞支持部材と、上記貫通スリーブの外周
に設けられ上記原子炉格納容器内に埋設される環
状のアンカープレートと、このアンカープレート
の側面に溶接結合され且つ上記原子炉格納容器外
に位置する貫通スリーブの外周に放射状の突設さ
れた複数の放熱フインとを具備したことを特徴と
するものである。
（作用）
本発明においては、原子炉格納容器外に位置す
る貫通スリーブの外周に複数の放熱フインを放射
状に突設することにより、貫通スリーブに伝わつ
た熱を放熱フインによつて原子炉格納容器外へ放
出させることができる。また、放熱フインはアン
カープレートの側面に溶接結合されているので、
アンカープレートの補強部材を兼ねることができ
る。
（実施例）
以下本発明を第３図および第４図に示す一実施
例にしたがつて説明する。図中１０１は原子炉格
納容器であつて、マツト１０２上に構築され、原
子炉建屋１０３内に収容されている。そして、こ
の原子炉格納容器１０１は鉄筋コンクリート製の
格納容器本体１０４とこの格納容器本体１０４の
内面に張られたライナー１０５とから構成されて
いる。この格納容器本体１０４は強固に形成さ
れ、耐圧性と遮蔽能力を備えている。また、上記
ライナー１０５は比較的薄い鋼板から形成され、
気密性を与えるとともに、格納容器本体１０４の
内面に密着しており、この原子炉格納容器１０１
内の圧力が上昇した場合でも圧力によつて変形し
ないように構成されている。
また、ライナー１０５の内面には型鋼等からな
る補強部材（図示せず）が取付けられており、格
納容器本体１０４との熱膨脹差によつてライナー
１０５に生じる荷重を受け、ライナー１０５の局
部的な変形等を防止している。そして、原子炉格
納容器１０１内はダイヤフラムフロア１０６によ
つて上下に区画され、上部はドライウエル１０
７、下部はサプレツシヨンチヤンバ１０８に形成
されている。また、原子炉格納容器１０１の底部
からはペデスタル１０９が立設され、このペデス
タル１０９上には原子炉圧力容器１１０が据付け
られている。
各種の配管たとえば主蒸気配管１１１は、配管
貫通装置１１２によつて原子炉格納容器１０１外
に導出されている。以下、この配管貫通装置１１
２の構成を説明する。図中１１３は貫通スリーブ
であつて円筒状をなしている。この貫通スリーブ
１１３は格納容器本体１０４内に埋め込まれ、格
納容器本体１０４およびライナー１０５を気密を
もつて貫通している。そして、貫通スリーブ１１
３はアンカー（図示せず）および格納容器本体１
０４に埋め込まれた円環状のアンカープレート１
１５によつて格納容器本体１０４に固定されてい
る。
また、貫通スリーブ１１３の原子炉格納容器外
側（第４図で右側）の端部は所定長さだけ原子炉
建屋１０３内に突出している。そして、貫通スリ
ーブ１１３内には主蒸気配管１１１が挿通され、
この主蒸気配管１１１の外周面と貫通スリーブ１
１３の内周面との間には断熱材１１７が設けられ
ている。この断熱材１１７は主蒸気配管１１１を
囲んで設けられた外囲管１１４内に設けられ、外
囲管１１４の端部は円環状のサポート板１１６に
よつて支持されている。
また、貫通スリーブ１１３の原子炉格納容器外
側端部には、閉塞支持部材１１８が設けられてい
る。この閉塞支持部材１１８は貫通スリーブ１１
３の端部および主蒸気配管１１１の外周面に溶接
され、この主蒸気配管１１１に作用する軸方向、
ねじり方向の荷重を貫通スリーブ１１３に伝える
とともにこの外側端部において主蒸気配管１１１
と貫通スリーブ１１３間の間隙を気密に閉塞して
いる。
貫通スリーブ１１３の外側端部の外周には多数
の放熱フイン１１９…が放射状に突設されてい
る。これら放熱フイン１１９…は鋼板からなり、
貫通スリーブ１１３の外周面に溶接されるととも
に前記アンカープレート１１５の側面に溶接さ
れ、このアンカープレート１１５と貫通スリーブ
１１３との取付を補強するガセツトを兼用してい
る。
以上の如く構成された本発明の一実施例は、ラ
イナー１０５、貫通スリーブ１１３および閉塞支
持部材１１８でこの部分の原子炉格納容器１０１
のバウンダリが形成され、この部分の気密性が維
持される。また、熱膨張等によつてこの主蒸気管
１１１に作用する軸方向の荷重やねじり荷重は閉
塞支持部材１１８、貫通スリーブ１１３を介して
格納容器本体１０４で受けられ、この主蒸気配管
１１１の変形が防止される。そして、この主蒸気
配管１１１の熱は閉塞支持部材１１８を介して貫
通スリーブ１１３に伝わり、さらにこの周囲の格
納容器本体１０４に伝わる。しかし、このものは
貫通スリーブ１１３の端部外周に多数の放熱フイ
ン１１９…が設けられているので、閉塞支持部材
１１８を介してこの貫通スリーブ１１３の端部に
伝えられた熱はこれら放熱フイン１１９…によつ
て放散される。したがつてこの貫通スリーブ１１
３の温度上昇は小さく、よつてその周囲の格納容
器本体１０４の温度上昇も小となり、コンクリー
トの強度低下を招くこともないのでこの部分の健
全性に悪影響を与えることがない。
［発明の効果］
上述の如く本発明は、コンクリート製の原子炉
格納容器を貫通して設けられた貫通スリーブと、
この貫通スリーブ内を間隙をもつて挿通された配
管と、この配管と上記貫通スリーブとの間隙を気
密に閉塞すると共に上記配管を支持する閉塞支持
部材と、上記貫通スリーブの外周に設けられ上記
原子炉格納容器内に埋設される環状のアンカープ
レートと、このアンカープレートの側面に溶接結
合され且つ上記原子炉格納容器外に位置する貫通
スリーブの外周に放射状に突設された複数の放熱
フインとを具備したものである。したがつて、閉
塞支持部材を介して貫通スリーブに伝わつた配管
の熱を放熱フインによつて原子炉格納容器外へ放
熱でき、貫通スリーブの温度上昇を防止すること
ができる。また、放熱フインはアンカープレート
の側面に溶接結合され、アンカープレートの補強
部材を兼ねているので、貫通スリーブを原子炉格
納容器に強固に固定することができる。 Detailed Description of the Invention [Object of the Invention] (Industrial Application Field) The present invention relates to a pipe penetration device in a concrete reactor containment vessel. (Conventional technology) Conventionally, a reactor containment vessel is made of steel that has pressure resistance and airtightness, and a concrete shielding wall is provided around it, which prevents coolant from leaking inside. It was used to prevent the spread of radioactive materials and to shield radiation. but,
This type of structure had the disadvantage of having a complicated structure and increasing construction costs. In place of such a steel reactor containment vessel, a concrete reactor containment vessel as shown in FIGS. 1 and 2 has been developed. That is, numeral 1 in the figure is the main body of the containment vessel, which is strongly formed of reinforced concrete or the like and has pressure resistance and radiation shielding ability. A liner 2 made of a relatively thin steel plate is provided in close contact with the inner surface of the containment vessel body 1 to provide airtightness. A reactor pressure vessel 3 is housed within this reactor containment vessel,
Further, a suppression chamber 4 is formed in the lower part. Further, a pipe, for example, a main steam pipe 5 passes through the reactor containment vessel via a pipe penetration device 6 . By the way, such a reactor containment vessel made of concrete has a simple structure, and the reactor containment vessel itself has sufficient strength and rigidity, so piping, etc. can be supported by this reactor containment vessel. There are advantages. In the conventional reactor, a pipe, for example, a main steam pipe 5, is supported in the reactor containment vessel via a pipe penetration device 6 , as shown in FIG. That is, 7 is a penetrating sleeve that is provided to penetrate the containment vessel main body 1 and the liner 2, and anchors 8... and anchor plates 9.
It is fixed to the containment vessel main body 1 by. The main steam pipe 5 is inserted through the through sleeve 7 with a gap therebetween. A closing support member 10 is provided at the end of the penetration sleeve 7 on the outside of the reactor containment vessel (right side in FIG. 2), and this closure support member 10 connects the penetration sleeve 7 and the main steam pipe. 5 is airtightly closed, and this main steam pipe 5 is supported by a through sleeve 7. Therefore, the axial load and torsional load generated on the main steam pipe 5 due to thermal expansion or the like are supported by the containment vessel main body 1 via the closure support member 10 and the through sleeve 7. (Problem to be Solved by the Invention) However, in such a system, the load of the main steam piping 5 is transmitted to the containment vessel main body 1 by the anchors 8 of the penetration sleeve 7 and the anchor plate 9. 1, a local load will act on this part. Further, since high-temperature steam flows through the main steam pipe 5, the heat is conducted to the through sleeve 7 via the closing support member 10, and is also transmitted to the through sleeve 7 by radiation and convection. For this reason, the temperature of the penetrating sleeve 7 increases, and the temperature of the surrounding containment vessel body 1 also increases, which may cause the strength of the concrete to decrease. For this reason, the health evaluation of the containment vessel body 1 in the vicinity of this piping penetration device 6 becomes more difficult.
There were problems such as the need to provide special reinforcement to the vicinity of the pipe penetration device 6 . For this reason, in the past, a heat insulating material was interposed between the main steam pipe 5 and the through sleeve 6 , but the effect was insufficient. In addition, a cooling pipe is provided between the main steam pipe 5 and the through sleeve 6 , and a refrigerant is circulated through this cooling pipe to prevent the temperature of the through sleeve 7 from rising, but such a system has a structure. There were problems such as complications. The present invention was made based on the above circumstances, and its purpose is to provide a pipe penetration device that does not adversely affect the integrity of a concrete reactor containment vessel and has a simple structure. be. [Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention includes a penetration sleeve provided to penetrate a concrete reactor containment vessel, and a space inside the penetration sleeve. A closing support member that airtightly closes a gap between the piping and the through sleeve and supports the piping, and a closing support member that is provided around the outer periphery of the through sleeve and is buried in the reactor containment vessel. The reactor is characterized by comprising: an annular anchor plate; and a plurality of heat dissipation fins welded to the side surface of the anchor plate and protruding radially from the outer periphery of the penetration sleeve located outside the reactor containment vessel. It is something. (Function) In the present invention, by providing a plurality of heat dissipation fins radially protruding from the outer periphery of the penetration sleeve located outside the reactor containment vessel, the heat transmitted to the penetration sleeve is transferred to the reactor containment vessel by the heat dissipation fins. It can be released outside. In addition, the heat dissipation fins are welded to the side of the anchor plate, so
It can also serve as a reinforcing member for the anchor plate. (Example) The present invention will be described below with reference to an example shown in FIGS. 3 and 4. In the figure, 101 is a reactor containment vessel, which is constructed on a mat 102 and housed in a reactor building 103. The reactor containment vessel 101 is composed of a containment vessel main body 104 made of reinforced concrete and a liner 105 stretched on the inner surface of the containment vessel main body 104. This containment vessel body 104 is strongly formed and has pressure resistance and shielding ability. Further, the liner 105 is formed from a relatively thin steel plate,
It provides airtightness and is in close contact with the inner surface of the containment vessel main body 104, and this reactor containment vessel 101
It is constructed so that it will not deform due to pressure even if the internal pressure increases. In addition, a reinforcing member (not shown) made of shaped steel or the like is attached to the inner surface of the liner 105, and receives the load generated on the liner 105 due to the difference in thermal expansion with the containment vessel main body 104. Prevents deformation etc. The inside of the reactor containment vessel 101 is divided into upper and lower parts by a diaphragm floor 106, and the upper part is divided into a dry well 10.
7. The lower part is formed into a suppression chamber 108. Further, a pedestal 109 is erected from the bottom of the reactor containment vessel 101 , and a reactor pressure vessel 110 is installed on this pedestal 109. Various types of piping, such as the main steam piping 111, are led out of the reactor containment vessel 101 by a piping penetration device 112 . Below, this pipe penetration device 11
The second configuration will be explained. In the figure, reference numeral 113 denotes a through sleeve, which has a cylindrical shape. This penetrating sleeve 113 is embedded within the containment vessel body 104 and passes through the containment vessel body 104 and the liner 105 in an airtight manner. And the penetrating sleeve 11
3 is an anchor (not shown) and the containment vessel body 1
Annular anchor plate 1 embedded in 04
15 to the containment vessel main body 104. Further, the end of the penetrating sleeve 113 on the outside of the reactor containment vessel (the right side in FIG. 4) protrudes into the reactor building 103 by a predetermined length. The main steam pipe 111 is inserted into the penetration sleeve 113,
The outer peripheral surface of this main steam pipe 111 and the penetration sleeve 1
A heat insulating material 117 is provided between the inner circumferential surface of 13 and the inner circumferential surface of 13 . This heat insulating material 117 is provided in an outer tube 114 surrounding the main steam pipe 111, and an end of the outer tube 114 is supported by an annular support plate 116. Further, a closing support member 118 is provided at the outer end of the reactor containment vessel of the penetrating sleeve 113. This closure support member 118 is connected to the penetrating sleeve 11
3 and the outer circumferential surface of the main steam pipe 111, and act on the main steam pipe 111 in the axial direction;
The torsional load is transmitted to the through sleeve 113 and the main steam pipe 111 is
The gap between the penetrating sleeve 113 and the penetrating sleeve 113 is hermetically closed. A large number of heat radiation fins 119 are provided radially projecting from the outer periphery of the outer end of the penetrating sleeve 113. These heat dissipation fins 119 are made of steel plates,
It is welded to the outer peripheral surface of the penetrating sleeve 113 and to the side surface of the anchor plate 115, and also serves as a gusset for reinforcing the attachment of the anchor plate 115 and the penetrating sleeve 113. In one embodiment of the present invention configured as described above, the liner 105, the penetrating sleeve 113, and the closing support member 118 are used in this part of the reactor containment vessel 101.
A boundary is formed and the airtightness of this area is maintained. In addition, axial loads and torsional loads acting on the main steam pipe 111 due to thermal expansion etc. are received by the containment vessel main body 104 via the closure support member 118 and the penetration sleeve 113, causing deformation of the main steam pipe 111. is prevented. The heat of this main steam pipe 111 is transmitted to the penetrating sleeve 113 via the closure support member 118, and further to the containment vessel body 104 surrounding this. However, since a large number of heat radiation fins 119 are provided on the outer periphery of the end of the penetrating sleeve 113, the heat transferred to the end of the penetrating sleeve 113 via the closing support member 118 is transferred to these heat radiation fins 119. Dissipated by... Therefore, this through sleeve 11
The temperature rise in No. 3 is small, and therefore the temperature rise in the surrounding containment vessel body 104 is also small, and the strength of the concrete does not decrease, so there is no adverse effect on the integrity of this part. [Effects of the Invention] As described above, the present invention includes a penetration sleeve provided through a concrete reactor containment vessel,
a pipe inserted with a gap in the through sleeve; a closing support member that airtightly closes the gap between the pipe and the through sleeve and supports the pipe; An annular anchor plate buried in the reactor containment vessel, and a plurality of heat dissipation fins welded to the side surface of the anchor plate and protruding radially from the outer periphery of a penetration sleeve located outside the reactor containment vessel. It is equipped with Therefore, the heat of the piping transmitted to the penetrating sleeve via the closing support member can be radiated to the outside of the reactor containment vessel by the heat radiating fin, and an increase in temperature of the penetrating sleeve can be prevented. In addition, the radiation fins are welded to the side surfaces of the anchor plate and also serve as reinforcing members for the anchor plate, so that the penetrating sleeve can be firmly fixed to the reactor containment vessel.
第１図および第２図は従来例を示し、第１図は
全体の縦断面図、第２図は配管貫通装置の縦断面
図である。第３図ないし第５図は本発明の一実施
例を示し、第３図は全体の縦断面図、第４図は配
管貫通装置の縦断面図、第５図は第４図のＶ−Ｖ
矢視図である。
１０１……原子炉格納容器、１０４……格納容
器本体、１０５……ライナー、１１１……主蒸気
配管（配管）、１１２……配管貫通装置、１１３
……貫通スリーブ、１１５……アンカープレー
ト、１１８……閉塞支持部材（支持部材）、１１
９……放熱フイン。
1 and 2 show a conventional example, with FIG. 1 being a longitudinal cross-sectional view of the whole, and FIG. 2 being a longitudinal cross-sectional view of a pipe penetration device. 3 to 5 show one embodiment of the present invention, FIG. 3 is a longitudinal sectional view of the whole, FIG. 4 is a longitudinal sectional view of a pipe penetration device, and FIG. 5 is a V-V of FIG. 4.
It is an arrow view. 101 ...Reactor containment vessel, 104...Containment vessel main body, 105...Liner, 111...Main steam piping (piping), 112 ...Piping penetration device, 113
... Penetration sleeve, 115 ... Anchor plate, 118 ... Closure support member (support member), 11
9... Heat dissipation fin.
Claims (1)
設けられた貫通スリーブと、この貫通スリーブ内
を間隙をもつて挿通された配管と、この配管と上
記貫通スリーブとの間隙を気密に閉塞すると共に
上記配管を支持する閉塞支持部材と、上記貫通ス
リーブの外周に設けられ上記原子炉格納容器内に
埋設される環状のアンカープレートと、このアン
カープレートの側面に溶接結合され且つ上記原子
炉格納容器外に位置する貫通スリーブの外周に放
射状に突設された複数の放熱フインとを具備した
ことを特徴とする原子炉格納容器の配管貫通装
置。1. A penetration sleeve provided through a concrete reactor containment vessel, a pipe inserted through the penetration sleeve with a gap, and a gap between the pipe and the penetration sleeve airtightly closed, and the above-mentioned a closing support member that supports the piping; an annular anchor plate provided on the outer periphery of the penetrating sleeve and buried within the reactor containment vessel; A piping penetration device for a nuclear reactor containment vessel, comprising a plurality of heat dissipation fins that protrude radially from the outer periphery of a penetration sleeve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56101613A JPS582793A (en) | 1981-06-30 | 1981-06-30 | Pipe through device of reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56101613A JPS582793A (en) | 1981-06-30 | 1981-06-30 | Pipe through device of reactor container |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS582793A JPS582793A (en) | 1983-01-08 |
| JPH0126436B2 true JPH0126436B2 (en) | 1989-05-23 |
Family
ID=14305246
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56101613A Granted JPS582793A (en) | 1981-06-30 | 1981-06-30 | Pipe through device of reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS582793A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104295800A (en) * | 2014-08-27 | 2015-01-21 | 中广核工程有限公司 | Structure and construction method for nuclear power plant heat preservation pipeline to penetrate through stainless steel cover face |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61230851A (en) * | 1985-04-08 | 1986-10-15 | Shibayama Kikai Kk | Polishing device for wafer on grinding machine |
| JPH0735724Y2 (en) * | 1988-01-20 | 1995-08-16 | アミテック株式会社 | Belt pressure pad device for belt sander |
| JPH0413562A (en) * | 1990-04-27 | 1992-01-17 | Nisshinbo Ind Inc | Multibelt grinding machine |
| JP7032915B2 (en) * | 2017-11-30 | 2022-03-09 | 三菱重工業株式会社 | Nuclear plant and sleeve cooling mechanism |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS50416A (en) * | 1972-12-14 | 1975-01-07 | ||
| US4134491A (en) * | 1978-02-24 | 1979-01-16 | The International Nickel Company, Inc. | Hydride storage containment |
-
1981
- 1981-06-30 JP JP56101613A patent/JPS582793A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS50416A (en) * | 1972-12-14 | 1975-01-07 | ||
| US4134491A (en) * | 1978-02-24 | 1979-01-16 | The International Nickel Company, Inc. | Hydride storage containment |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104295800A (en) * | 2014-08-27 | 2015-01-21 | 中广核工程有限公司 | Structure and construction method for nuclear power plant heat preservation pipeline to penetrate through stainless steel cover face |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS582793A (en) | 1983-01-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US3488067A (en) | Air cooled pipe penetrations in concrete walls | |
| RU2348085C1 (en) | Container for transportation and/or storage of waste nuclear fuel | |
| JPH0126436B2 (en) | ||
| US3712012A (en) | Reinforced-concrete pressure vessel with lining | |
| US4356144A (en) | Closure hold-down system for a reactor vessel | |
| US3471599A (en) | Method of constructing a containment and radiation shielding system | |
| US4223496A (en) | High pressure, high-temperature vessel, especially for nuclear reactors | |
| JPH0128276B2 (en) | ||
| JPH08160177A (en) | Structure of piping penetration part in reactor containment | |
| JPH048397Y2 (en) | ||
| JPH0350480Y2 (en) | ||
| JPS582791A (en) | Pipe through device of reactor container | |
| JPH0336781Y2 (en) | ||
| JP2002189097A (en) | Concrete storage container | |
| JP2803330B2 (en) | gasket | |
| JP2021177150A (en) | Cask | |
| JPH0612886U (en) | Structure of wall penetration of piping | |
| JPH01187498A (en) | Reactor container made of concrete | |
| JPH0458917B2 (en) | ||
| JPS6339678Y2 (en) | ||
| JPS5834397A (en) | Tank for liquid storage | |
| JPS5946887A (en) | Concrete container penetration for reactor | |
| JPS608786A (en) | Containing vessel structure of nuclear reactor | |
| JPS6185597A (en) | Flexible supporting equipment for vertical pump | |
| JPS6346392B2 (en) |