JPS6193998A - Method of overhauling nuclear reactor container made of prestressed concrete - Google Patents

Method of overhauling nuclear reactor container made of prestressed concrete

Info

Publication number
JPS6193998A
JPS6193998A JP21534184A JP21534184A JPS6193998A JP S6193998 A JPS6193998 A JP S6193998A JP 21534184 A JP21534184 A JP 21534184A JP 21534184 A JP21534184 A JP 21534184A JP S6193998 A JPS6193998 A JP S6193998A
Authority
JP
Japan
Prior art keywords
concrete
containment vessel
reactor containment
prestressed concrete
wall
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
Application number
JP21534184A
Other languages
Japanese (ja)
Inventor
渡辺 貴明
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
IHI Corp
Original Assignee
IHI Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by IHI Corp filed Critical IHI Corp
Priority to JP21534184A priority Critical patent/JPS6193998A/en
Publication of JPS6193998A publication Critical patent/JPS6193998A/en
Pending legal-status Critical Current

Links

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 「産業上の利用分野」 本発明はプレストレストコンクリート製原子炉格納容器
の解体方法に関する。
DETAILED DESCRIPTION OF THE INVENTION "Field of Industrial Application" The present invention relates to a method for dismantling a reactor containment vessel made of prestressed concrete.

「従来の技術j プレストレストコンクリートは、コンクリート壁に高張
力鋼材(以下pci材という)によって予め圧縮応力を
付与させておくことにより、引張り強度が低いというコ
ンクリートの欠点を補い、設計荷重の範囲内ではコンク
リート壁に引張り応力が生じ得ない状聾にして各種構造
物の機械的強度を高めるもので、高い内圧強度を必要と
する原子炉格納容器の壁にも適用が図られている。
``Prestressed concrete'' compensates for concrete's low tensile strength by pre-applying compressive stress to the concrete wall using high-tensile steel (hereinafter referred to as PCI material). This technology increases the mechanical strength of various structures by preventing tensile stress from occurring in concrete walls, and is also being applied to the walls of nuclear reactor containment vessels, which require high internal pressure strength.

ところで、このようなプレストレストコンクリートによ
り構築された原子炉格納容器をその耐用年数経過後に解
体する場合、例えばコンクリート破砕機等を使用して、
コンクリート壁に衝撃、振動等を与えることにより、ク
ラックを発生させて破壊することが考えられる。
By the way, when dismantling a reactor containment vessel constructed from such prestressed concrete after its useful life has elapsed, for example, using a concrete crusher, etc.
It is conceivable that applying impact, vibration, etc. to a concrete wall can cause cracks to occur and cause it to break.

「発明が解決しようとする問題点」 しかしながら、このような解体方法では、プレストレス
による圧縮応力を上回りかつコーンクリート壁にクラッ
クを生じさせ得る引張り応力を発生させることは容易で
なく、破壊に至るまでに多くの労力を必要とし、作業時
間が長くなるという問題が生じ易い。特に、原子炉格納
容器に放射性物質が残留していると、解体作業における
被ばく線色の増大を招くおそれがある。
``Problems to be Solved by the Invention'' However, with this type of demolition method, it is not easy to generate tensile stress that exceeds the compressive stress caused by prestress and can cause cracks in the conecrete wall, leading to fracture. The problem is that it requires a lot of effort and takes a long time. In particular, if radioactive materials remain in the reactor containment vessel, there is a risk of an increase in radiation exposure during demolition work.

本発明は前記問題点を有効に解決するもので、プレスト
レストコンクリート壁に引張り応力を生じさせることを
容易にして、破壊に要する力を低減させ、解体作業の能
率を向上させて作業時間を短縮することを目的とする。
The present invention effectively solves the above problems, and facilitates the generation of tensile stress in prestressed concrete walls, reducing the force required for destruction, improving the efficiency of demolition work, and shortening the work time. The purpose is to

「問題点を解決するための手段」 本発明は、プレストレスを付与しているPCM材の緊張
を解放してコンクリート壁に引張り応力を発生させ易い
状態にしてから、該コンクリート壁にプレストレスが作
用していた方向と反対方向の引張り応力を発生させてこ
れを破壊するものである。
"Means for Solving the Problems" The present invention releases the tension of the PCM material applying prestress to make it easy to generate tensile stress in the concrete wall, and then prestresses the concrete wall. This creates a tensile stress in the opposite direction to the direction in which it was acting, causing it to break.

「実施例」 以下、本発明の一実施例を図面に基づいて説明する。"Example" Hereinafter, one embodiment of the present invention will be described based on the drawings.

まず、本発明の方法が適用される原子炉格納容器の例に
ついて説明する。該原子炉格納容器の壁は、基礎lの上
にPC鋼材2を7−ス管3に挿入した状態で縦横に配設
することにより、第1図に示すようなドーム状の鋼材壁
4を構築しておき、該鋼材壁4の両面に型枠(図示路)
を配設しながらコンクリートを打設して固化させた後、
第2図および第3図に示すように、各pca材2を緊張
してその両端をねじあるいはくさび等を利用した定着金
具5によりコンクリート壁6に定着するとともに、pc
a材2とノース管3との間をグラウト7により充填して
なるもので、コンクリート壁6にpca材2に沿゛う圧
縮応力を生じさせておくことにより、原子炉格納容器内
の万一の事故に対する高い内圧強度を確保したものであ
る。
First, an example of a nuclear reactor containment vessel to which the method of the present invention is applied will be described. The walls of the reactor containment vessel are constructed by arranging prestressing steel materials 2 vertically and horizontally on the foundation 1 with 7-spring pipes 3 inserted, thereby creating a dome-shaped steel wall 4 as shown in Fig. 1. The steel wall 4 is constructed in advance, and formwork (as shown in the diagram) is installed on both sides of the steel wall 4.
After pouring and hardening concrete while placing
As shown in FIGS. 2 and 3, each PCA material 2 is tensioned and its both ends are fixed to a concrete wall 6 with fixing fittings 5 using screws or wedges, etc.
The space between the A material 2 and the north pipe 3 is filled with grout 7, and by creating compressive stress along the PCA material 2 in the concrete wall 6, it is possible to prevent any damage inside the reactor containment vessel. This ensures high internal pressure strength against accidents.

次いで、このような原子炉格納容器を解体する方法につ
いて説明する。
Next, a method for dismantling such a reactor containment vessel will be explained.

まず、定着金具5を除去して各20w4材2の緊張を解
放することにより、PC鋼材2に沿って作用していたプ
レストレスすなわち圧縮応力をコンクリート壁6から除
去するとともに、ツヤツキ等を使用して適宜pca材2
をノース管3から引き抜く。
First, by removing the fixing fittings 5 and releasing the tension in each 20w4 material 2, the prestress that was acting along the PC steel material 2, that is, the compressive stress, is removed from the concrete wall 6, and at the same time, using gloss etc. PCA material 2 as appropriate
Pull it out from the north pipe 3.

そして、第4図に示すように、原子炉格納容器に例えば
水圧等による内圧p。をかけると、プレストレスの解放
により強度が低下させられたコンクリート壁6に、プレ
ストレスが作用していた方向と反対方向の応力つまり引
張り応力p1がPC鋼材2を引き抜いた後の孔に沿って
発生し、該引張り応力p1によりフンクーリート壁6に
クランクCが生して破壊に至るものである。また、原子
炉格納容器に内圧をかける作業は、内部に原子炉運転中
の万一の事故に備えてサブレブノコンチェンバと称され
る部分に冷却水を常時貯留した構造の原子炉格納容器の
場合には、冷却水に水を注ぎ足すことにより、能卆良く
内圧をかけることができる。
Then, as shown in FIG. 4, an internal pressure p is applied to the reactor containment vessel due to, for example, water pressure. When the prestress is released, a stress in the opposite direction to the direction in which the prestress was applied, that is, a tensile stress p1, is applied to the concrete wall 6, whose strength has been reduced due to the release of the prestress, along the hole after the prestressed steel material 2 is pulled out. The tensile stress p1 causes a crank C to form in the Hungkurito wall 6, leading to its destruction. In addition, the work to apply internal pressure to the reactor containment vessel is carried out in the reactor containment vessel, which has a structure in which cooling water is permanently stored in a part called a sub-reconchamber in case of an accident during reactor operation. In such cases, internal pressure can be efficiently applied by adding water to the cooling water.

なお、緊張を解放した後のPC鋼材2の一部をコンクリ
ート壁6の中に残しておくことにより、該pca材2に
より連結した状態でコンクリート壁6を破壊して、破片
等の飛散を効果的に抑制することができる。また、コン
クリート破砕機等により局部的に衝撃、振動等を与える
などの補助的な手段を用いて、コノクリート壁6を破壊
することら可能である。
In addition, by leaving a part of the PC steel material 2 in the concrete wall 6 after releasing the tension, the concrete wall 6 can be destroyed while connected by the PCA material 2, and debris etc. can be effectively prevented from scattering. can be suppressed. It is also possible to destroy the conocrete wall 6 using auxiliary means such as locally applying impact, vibration, etc. using a concrete crusher or the like.

「発明の効果」 以上説明したように、本発明のプレストレストコノクリ
ート製原子炉格納容器の解体方法によれば、予めpca
材の緊張を緩めて、該PCM材に沿って作用しているプ
レストレスを解放させることにより、コンクリート壁に
引張り応力を発生させ易い状態にしてから、該コンクリ
ート壁にプレストレスが作用していた方向と反対方向の
引張り応力を発生させて破壊するようにして、破壊に要
する力を低減させ得て、解体作業の能率を向上させ、作
業時間の短縮を図ることができるという効果を奏する。
"Effects of the Invention" As explained above, according to the method for dismantling a reactor containment vessel made of prestressed conocret of the present invention, pca
By relaxing the tension in the PCM material and releasing the prestress acting along the PCM material, the concrete wall was in a state where it was easy to generate tensile stress, and then the prestress was applied to the concrete wall. By generating tensile stress in the opposite direction to the fracture, the force required for the fracture can be reduced, and the efficiency of disassembly work can be improved and the working time can be shortened.

【図面の簡単な説明】[Brief explanation of drawings]

図面は本発明の一実施例を示すもので、第1図は本発明
が適用される原子炉格納容器におけるPC&Il材の配
設例を示す斜視図、第2図は原子炉格納容器の壁の横断
面図、第3図は第2図の鎖線■で示す部分の拡大図、第
4図は破壊時の作用を説明するために示した原子炉格納
容器の壁の一部省略横断面図である。 1・ 基礎、2  ・4’CMH13ノース管、4  
鋼材壁、5 ・・定着金具、6  コンクリート壁、7
 ・・・グラウト、C・・クラック。 出願人  石川島播磨重工業株式会社 第1図
The drawings show one embodiment of the present invention. Fig. 1 is a perspective view showing an example of the arrangement of PC&Il materials in a reactor containment vessel to which the present invention is applied, and Fig. 2 is a cross-sectional view of the wall of the reactor containment vessel. Fig. 3 is an enlarged view of the part indicated by the chain line ■ in Fig. 2, and Fig. 4 is a partially omitted cross-sectional view of the wall of the reactor containment vessel shown to explain the action at the time of destruction. . 1. Basics, 2. 4'CMH13 north tube, 4
Steel wall, 5...Fixing metal fittings, 6 Concrete wall, 7
... Grout, C... Crack. Applicant Ishikawajima Harima Heavy Industries Co., Ltd. Figure 1

Claims (1)

【特許請求の範囲】[Claims] プレストレストコンクリート製原子炉格納容器の解体方
法において、コンクリート壁にプレストレスを付与して
いる高張力鋼材の緊張を解放した後、該コンクリート壁
に前記プレストレスが作用していた方向と反対方向の引
張り応力を発生させてこれを破壊することを特徴とする
プレストレストコンクリート製原子炉格納容器の解体方
法。
In a method for dismantling a reactor containment vessel made of prestressed concrete, after releasing the tension of the high-tensile steel material that applies prestress to the concrete wall, the concrete wall is pulled in the opposite direction to the direction in which the prestress was acting. A method for dismantling a reactor containment vessel made of prestressed concrete, characterized by generating stress and destroying it.
JP21534184A 1984-10-15 1984-10-15 Method of overhauling nuclear reactor container made of prestressed concrete Pending JPS6193998A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP21534184A JPS6193998A (en) 1984-10-15 1984-10-15 Method of overhauling nuclear reactor container made of prestressed concrete

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP21534184A JPS6193998A (en) 1984-10-15 1984-10-15 Method of overhauling nuclear reactor container made of prestressed concrete

Publications (1)

Publication Number Publication Date
JPS6193998A true JPS6193998A (en) 1986-05-12

Family

ID=16670693

Family Applications (1)

Application Number Title Priority Date Filing Date
JP21534184A Pending JPS6193998A (en) 1984-10-15 1984-10-15 Method of overhauling nuclear reactor container made of prestressed concrete

Country Status (1)

Country Link
JP (1) JPS6193998A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5329562A (en) * 1991-08-26 1994-07-12 Kabushiki Kaisha Dymosha Method of cutting and removing nuclear reactor
JPH0711778A (en) * 1993-06-25 1995-01-13 Kajima Corp Demolition work method for reinforced concrete building
JP2002323593A (en) * 2001-04-27 2002-11-08 Ishikawajima Harima Heavy Ind Co Ltd Concrete cask

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5329562A (en) * 1991-08-26 1994-07-12 Kabushiki Kaisha Dymosha Method of cutting and removing nuclear reactor
JPH0711778A (en) * 1993-06-25 1995-01-13 Kajima Corp Demolition work method for reinforced concrete building
JP2002323593A (en) * 2001-04-27 2002-11-08 Ishikawajima Harima Heavy Ind Co Ltd Concrete cask

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