JP2962913B2 - Reactor building - Google Patents
Reactor buildingInfo
- Publication number
- JP2962913B2 JP2962913B2 JP3353653A JP35365391A JP2962913B2 JP 2962913 B2 JP2962913 B2 JP 2962913B2 JP 3353653 A JP3353653 A JP 3353653A JP 35365391 A JP35365391 A JP 35365391A JP 2962913 B2 JP2962913 B2 JP 2962913B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- concrete structure
- containment vessel
- building
- internal concrete
- 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 - Fee Related
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
- Vibration Prevention Devices (AREA)
- Buildings Adapted To Withstand Abnormal External Influences (AREA)
Description
【0001】[0001]
【産業上の利用分野】本発明は、原子炉建屋における内
部コンクリート構造体の地震荷重を低減化させた原子炉
建屋に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor building in which an internal concrete structure in a reactor building has a reduced seismic load.
【0002】[0002]
【従来の技術とその問題点】加圧水型原子炉の建屋は、
図1に示すように各々の上部構造が独立した原子炉格納
容器1、内部コンクリート構造体2および原子炉周辺建
屋3により構成され、内部コンクリート構造体2には原
子炉4および蒸気発生器5などの重要機器が支持されて
いる。また、原子炉建屋は、その耐震安全性の観点か
ら、固い岩盤上に基礎版6を設置し、この基礎版6上に
前記原子炉格納容器1、内部コンクリート構造体2およ
び原子炉周辺建屋3が設けられている。この原子炉建屋
には地震に対して強度で対抗する、所謂耐震設計手法が
採用されているが、地震時における原子炉建屋の応答
(加速度、応力等)は非常に大きくなる。[Prior art and its problems] The building of a pressurized water reactor is
As shown in FIG. 1, each upper structure is composed of an independent reactor containment vessel 1, an internal concrete structure 2, and a building 3 around the reactor. The internal concrete structure 2 includes a reactor 4, a steam generator 5, and the like. Important equipment is supported. In addition, from the viewpoint of the seismic safety of the reactor building, the base plate 6 is installed on a solid rock, and the reactor containment vessel 1, the internal concrete structure 2, and the building 3 around the reactor are placed on the base plate 6. Is provided. This reactor building employs a so-called seismic design method that resists earthquakes with strength, but the response (acceleration, stress, etc.) of the reactor building during an earthquake becomes extremely large.
【0003】更に、地震時における原子炉建屋の応答挙
動は、基礎版6を地震の入力位置とした場合、原子炉格
納容器1、内部コンクリート構造体2および原子炉周辺
建屋3は単独で揺れるのに対して、原子炉4や蒸気発生
器5などの機器は内部コンクリート構造体2の振動の影
響を受ける。このため、原子炉4、蒸気発生器5および
これらの支持構造物は、この地震時の振動による影響に
耐えるための耐震設計が要求される結果、事故時の設計
条件から決定されるよりも過大な設計となることがあ
る。[0003] Furthermore, the response behavior of the reactor building during an earthquake is such that when the base plate 6 is used as an earthquake input position, the reactor containment vessel 1, the internal concrete structure 2, and the building 3 around the reactor sway independently. On the other hand, equipment such as the reactor 4 and the steam generator 5 is affected by the vibration of the internal concrete structure 2. For this reason, the reactor 4, the steam generator 5, and their supporting structures are required to have seismic design to withstand the effects of the vibration during the earthquake, and as a result, the reactor 4 and the steam generator 5 are larger than those determined from the design conditions at the time of the accident. May be a simple design.
【0004】[0004]
【発明の目的】本発明は前記課題を解決しようとするも
のであり、その目的は、内部コンクリート構造体2の地
震時の応答量を低減し、以て、内部コンクリート構造体
2、原子炉4、蒸気発生器5およびその支持構造物の合
理的な耐震設計を行うことにある。SUMMARY OF THE INVENTION It is an object of the present invention to solve the above-mentioned problems, and an object of the present invention is to reduce the response of an internal concrete structure 2 during an earthquake. , And a reasonable seismic design of the steam generator 5 and its supporting structure.
【0005】[0005]
【発明の構成】本発明は、原子炉と蒸気発生器を支持す
る内部コンクリート構造体を、原子炉格納容器内に有す
る原子炉建屋において、前記内部コンクリート構造体の
外周部から原子炉格納容器に向けてコンクリート製床版
を水平に突設させ、該床版と原子炉格納容器の内壁との
間に制振装置を設置したことを特徴とするものである。
前記制振装置は、積層鋼板間に粘弾性シートを挟み込ん
でなるものであることが好ましい。SUMMARY OF THE INVENTION The present invention relates to a reactor building having an internal concrete structure for supporting a nuclear reactor and a steam generator in a reactor containment vessel, and from an outer peripheral portion of the internal concrete structure to the reactor containment vessel. A concrete floor slab protrudes horizontally toward the slab, and a vibration damping device is installed between the floor slab and the inner wall of the containment vessel.
It is preferable that the vibration damping device has a viscoelastic sheet sandwiched between laminated steel sheets.
【0006】[0006]
【作用】地震時における、原子炉格納容器の応答量が内
部コンクリート構造体の応答を制限するため、内部コン
クリート構造体の応答量は従来よりも大幅に減少する。The amount of response of the containment vessel during an earthquake limits the response of the internal concrete structure, so that the amount of response of the internal concrete structure is significantly reduced.
【0007】[0007]
【実施例】以下、本発明に係る原子炉建屋の好ましい実
施例を図面に基づいて説明する。図1は原子炉建屋の概
略断面図であり、基礎版6上に原子炉格納容器1、内部
コンクリート構造体2および原子炉周辺建屋3が設置さ
れ、垂直筒状に立設された内部コンクリート構造体2に
は原子炉4および蒸気発生器5などの重要機器が支持さ
れている。また、内部コンクリート構造体2の外周部の
ほぼ中央部から、原子炉格納容器1に向けてコンクリー
ト製の床版7が水平に突設されている。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Preferred embodiments of the reactor building according to the present invention will be described below with reference to the drawings. FIG. 1 is a schematic cross-sectional view of a reactor building, in which a reactor containment vessel 1, an internal concrete structure 2, and a building 3 around a reactor are installed on a base plate 6, and an internal concrete structure erected in a vertical cylindrical shape. The body 2 supports important equipment such as a reactor 4 and a steam generator 5. A floor slab 7 made of concrete is horizontally protruded from a substantially central portion of the outer peripheral portion of the internal concrete structure 2 toward the containment vessel 1.
【0008】前記したように、従来の原子炉建屋では、
原子炉格納容器1と内部コンクリート構造体2の上部構
造はそれぞれ独立していたのであるが、本発明では、両
者を制振装置により接続するものである。As described above, in a conventional reactor building,
Although the upper structures of the containment vessel 1 and the internal concrete structure 2 were independent of each other, in the present invention, both are connected by a vibration damping device.
【0009】図2は原子炉格納容器1の内壁とコンクリ
ート製の床版7の間に設置した制振装置10の拡大図で
ある。制振装置10としては種々の形式のものを採用し
得るがここでは一例として、一対の積層鋼板11aおよ
び11b間に粘弾性シート12を挟み込み、その粘性抵
抗によって振動を吸収するものである。積層鋼板11a
の支持板13aは、原子炉格納容器1の内壁に埋込みボ
ルト14aで固着された固定板15aにボルト16aに
て固定されている。また、積層鋼板11bの支持板13
bは、床版7の外周部に埋込みボルト14bで固着され
た固定板15bに図示してないボルトにて固定されてい
る。従って、積層鋼板11aと11bとは粘弾性シート
12を介して、それぞれ独立して水平移動することにな
り、この結果、粘弾性シート12に生じる履歴が振動エ
ネルギーを吸収することになる。FIG. 2 is an enlarged view of the vibration damping device 10 installed between the inner wall of the containment vessel 1 and the concrete floor slab 7. As the vibration damping device 10, various types can be adopted. Here, as an example, a vibration-absorbing sheet 12 is interposed between a pair of laminated steel plates 11a and 11b, and the vibration is absorbed by viscous resistance. Laminated steel sheet 11a
The supporting plate 13a is fixed by bolts 16a to a fixing plate 15a fixed to the inner wall of the reactor containment vessel 1 by embedding bolts 14a. The support plate 13 of the laminated steel plate 11b
b is fixed to a fixing plate 15b fixed to the outer peripheral portion of the floor slab 7 by embedding bolts 14b with bolts (not shown). Therefore, the laminated steel plates 11a and 11b move horizontally independently via the viscoelastic sheet 12, and as a result, the history generated in the viscoelastic sheet 12 absorbs vibration energy.
【0010】図3は、図2のIII−III線における切断断
面図であり、制振装置10は振動実験や地震応答解析の
結果に基づいて、床版7の外周部の全周に亘って適宜の
間隔を置いて、水平方向に均等の性能となるように設置
する。制振装置10の設置方法としては、上記図2およ
び図3以外にも変更可能であり、例えば、各制振装置1
0を90°回転させて設置することにより、水平方向お
よび上下方向の地震時荷重を低減することも可能であ
る。FIG. 3 is a cross-sectional view taken along the line III-III of FIG. 2. The vibration damping device 10 extends over the entire outer periphery of the floor slab 7 based on the results of vibration tests and seismic response analysis. At appropriate intervals, they are installed so as to provide uniform performance in the horizontal direction. The installation method of the vibration damping device 10 can be changed to a method other than the above-described FIGS. 2 and 3.
By rotating 0 at 90 °, it is possible to reduce the horizontal and vertical loads during an earthquake.
【0011】原子炉格納容器1内は恒温でも50℃程度
あり、かつ、放射線レベルも高いから、制振装置10は
この環境に適合したものでなければならない。本実施例
では、粘弾性シート12として、実験により高温下にて
も耐劣化性の高い結果が得られたシリコン系ゴムを採用
した。なお、この粘弾性シート12は微小変形領域でも
履歴減衰効果が顕著であり、所期の目的を達成したこと
を確認した。Since the inside of the containment vessel 1 has a constant temperature of about 50 ° C. and a high radiation level, the vibration damping device 10 must be suitable for this environment. In the present embodiment, as the viscoelastic sheet 12, a silicon-based rubber that has obtained a high resistance to deterioration even at high temperatures by an experiment was employed. The viscoelastic sheet 12 has a remarkable hysteresis damping effect even in a minute deformation region, and it was confirmed that the intended purpose was achieved.
【0012】また、制振装置10の上方部には放射線を
遮蔽する目的で、伸縮自在のカバー17を設けて、放射
線による劣化を防止した。A telescopic cover 17 is provided above the vibration damping device 10 for the purpose of shielding radiation to prevent deterioration due to radiation.
【0013】[0013]
【発明の効果】本発明に係る原子炉建屋は、簡易な構成
によって内部コンクリート構造体の地震時の応答量を低
減させることができる。従って、従来の原子炉建屋の基
本設計思想を変更することなく、内部コンクリート構造
体、その他の支持構造物の合理的な耐震設計が可能とな
る。The reactor building according to the present invention can reduce the response of an internal concrete structure during an earthquake with a simple configuration. Therefore, rational earthquake-resistant design of the internal concrete structure and other supporting structures can be performed without changing the basic design concept of the conventional reactor building.
【図1】原子炉建屋の概略断面図である。FIG. 1 is a schematic sectional view of a reactor building.
【図2】制振装置とその設置部の拡大図である。FIG. 2 is an enlarged view of a vibration damping device and an installation portion thereof.
【図3】図2のIII−III線における制振装置の切断断面
図である。FIG. 3 is a cross-sectional view of the vibration damping device taken along the line III-III in FIG. 2;
1 原子炉格納容器 2 内部コンクリート構造体 3 原子炉周辺建屋 6 基礎版 7 床版 10 制振装置 11 積層鋼板 12 粘弾性シート REFERENCE SIGNS LIST 1 reactor containment vessel 2 internal concrete structure 3 building around reactor 6 base slab 7 floor slab 10 damping device 11 laminated steel plate 12 viscoelastic sheet
───────────────────────────────────────────────────── フロントページの続き (72)発明者 前川 利雄 東京都新宿区津久戸町2番1号 株式会 社熊谷組 東京本社内 (72)発明者 樺山 健太 東京都千代田区丸の内二丁目5番1号 三菱重工業株式会社内 (72)発明者 仲戸川 哲人 東京都港区芝公園二丁目4番1号 三菱 原子力工業株式会社内 (72)発明者 福西 史郎 東京都港区芝公園二丁目4番1号 三菱 原子力工業株式会社内 (56)参考文献 特開 昭51−137089(JP,A) 特開 昭62−259093(JP,A) 実開 昭61−173099(JP,U) (58)調査した分野(Int.Cl.6,DB名) G21C 13/024 GDP E04B 1/20 E04H 9/02 351 F16F 15/02 G21C 13/00 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Inventor Toshio Maekawa 2-1 Tsukudo-cho, Shinjuku-ku, Tokyo Tokyo Head Office (72) Inventor Kenta Kabayama 2-5-1 Marunouchi, Chiyoda-ku, Tokyo Inside Mitsubishi Heavy Industries, Ltd. (56) References JP-A-51-137089 (JP, A) JP-A-62-250993 (JP, A) Jpn. Sho 61-173099 (JP, U) (58) Fields investigated (Int.Cl. 6 , DB name) G21C 13/024 GDP E04B 1/20 E04H 9/02 351 F16F 15/02 G21C 13/00
Claims (2)
クリート構造体を、原子炉格納容器内に有する原子炉建
屋において、前記内部コンクリート構造体の外周部から
原子炉格納容器に向けてコンクリート製床版を水平に突
設させ、該床版と原子炉格納容器の内壁との間に制振装
置を設置したことを特徴とする原子炉建屋。 In a reactor building having an internal concrete structure supporting a nuclear reactor and a steam generator in a reactor containment vessel, from an outer peripheral portion of the internal concrete structure.
Project the concrete floor slab horizontally into the PCV.
Is set, reactor construction shop, characterized in that installed damping device between the floor plate and the containment vessel of the inner wall.
トを挟み込んでなるものである請求項1記載の原子炉建
屋。2. A viscoelastic seal between laminated steel sheets, wherein
The reactor building according to claim 1, wherein the reactor is sandwiched between the reactors.
Ya .
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3353653A JP2962913B2 (en) | 1991-12-18 | 1991-12-18 | Reactor building |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3353653A JP2962913B2 (en) | 1991-12-18 | 1991-12-18 | Reactor building |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH05164876A JPH05164876A (en) | 1993-06-29 |
JP2962913B2 true JP2962913B2 (en) | 1999-10-12 |
Family
ID=18432307
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP3353653A Expired - Fee Related JP2962913B2 (en) | 1991-12-18 | 1991-12-18 | Reactor building |
Country Status (1)
Country | Link |
---|---|
JP (1) | JP2962913B2 (en) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR20030039056A (en) * | 2001-11-09 | 2003-05-17 | 한국수력원자력 주식회사 | Reactor structure inner type refueling water storage tank for nuclear fuel of nuclear power plant |
KR100517121B1 (en) * | 2001-11-09 | 2005-09-27 | 한국수력원자력 주식회사 | Reactor structure inner type refueling water storage tank for nuclear fuel of nuclear power plant |
CN110106921B (en) * | 2019-05-14 | 2021-04-06 | 哈尔滨工程大学 | Foundation shock insulation and three-dimensional shock absorption structure of double-containment nuclear power station |
-
1991
- 1991-12-18 JP JP3353653A patent/JP2962913B2/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
JPH05164876A (en) | 1993-06-29 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
A01 | Written decision to grant a patent or to grant a registration (utility model) |
Free format text: JAPANESE INTERMEDIATE CODE: A01 Effective date: 19990706 |
|
LAPS | Cancellation because of no payment of annual fees |