JP3340871B2 - Reactor containment vessel - Google Patents
Reactor containment vesselInfo
- Publication number
- JP3340871B2 JP3340871B2 JP31620794A JP31620794A JP3340871B2 JP 3340871 B2 JP3340871 B2 JP 3340871B2 JP 31620794 A JP31620794 A JP 31620794A JP 31620794 A JP31620794 A JP 31620794A JP 3340871 B2 JP3340871 B2 JP 3340871B2
- Authority
- JP
- Japan
- Prior art keywords
- steel beam
- containment vessel
- steel
- reactor pressure
- floor
- 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
- 229910000831 Steel Inorganic materials 0.000 claims description 68
- 239000010959 steel Substances 0.000 claims description 68
- 230000001629 suppression Effects 0.000 claims description 14
- 239000004567 concrete Substances 0.000 claims description 10
- 238000010586 diagram Methods 0.000 claims description 6
- 230000003014 reinforcing effect Effects 0.000 claims description 5
- 229910003460 diamond Inorganic materials 0.000 description 15
- 239000010432 diamond Substances 0.000 description 15
- 238000010276 construction Methods 0.000 description 13
- 230000000694 effects Effects 0.000 description 5
- 238000000034 method Methods 0.000 description 4
- 239000011150 reinforced concrete Substances 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 238000005266 casting Methods 0.000 description 2
- 102200052313 rs9282831 Human genes 0.000 description 2
- 238000004378 air conditioning Methods 0.000 description 1
- 210000000988 bone and bone Anatomy 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 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 1
- 238000005192 partition Methods 0.000 description 1
- 239000012857 radioactive material Substances 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION
【0001】[0001]
【産業上の利用分野】本発明はダイヤフロムフロアの構
築時の作業量を低減した沸騰水型原子炉用原子炉格納容
器に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a containment vessel for a boiling water reactor, which reduces the amount of work required when constructing a diamond from floor.
【0002】[0002]
【従来の技術】原子炉一次系の万一の破損事故に際し、
炉心から漏出した放射性物質を系内に封じ込め、外部に
放射能を放出させないように原子炉格納容器を設けてい
る。沸騰水型原子炉の原子炉格納容器は全て圧力抑制式
で、ドライウェルと圧力抑制室から構成されている。2. Description of the Related Art In the event of an accidental damage to the primary reactor system,
The reactor containment vessel is provided so that radioactive materials leaked from the reactor core are contained in the system and radioactivity is not released outside. The reactor containment vessel of the boiling water reactor is all pressure suppression type, and consists of a drywell and a pressure suppression chamber.
【0003】ドライウェルには原子炉圧力容器,再循環
系機器配管,蒸気系配管、弁等原子炉圧力バウンダリに
属する設備のほか、原子炉圧力容器基礎台(ペデスタ
ル),熱遮蔽等の格納容器内部構造物,空調設備が収納
され、その大きさは安全性にかかわる要求の他に、配
管,据付け,保守点検等に必要なスペースも確保するよ
うに決められている。[0003] In the drywell, in addition to equipment belonging to the reactor pressure boundary such as a reactor pressure vessel, recirculation system piping, steam piping, and valves, a reactor pressure vessel base (pedestal), and a containment vessel such as a heat shield. The internal structure and the air-conditioning equipment are housed, and the size is determined so as to secure the space required for piping, installation, maintenance, and the like, in addition to the requirements related to safety.
【0004】図4に示すように沸騰水型原子炉における
鉄筋コンクリート製原子炉格納容器1は、内部中央に鋼
製原子炉圧力容器基礎台2の上部に原子炉圧力容器3が
設置されており、この鋼製原子炉圧力容器基礎台2と原
子炉圧力容器3の空間を上下にドライウェル4とサプレ
ッションプール5に区画する鉄筋コンクリートスラブに
よるダイヤフロムフロア6が構築されている。As shown in FIG. 4, a reinforced concrete reactor containment vessel 1 in a boiling water reactor has a reactor pressure vessel 3 installed above a steel reactor pressure vessel base 2 in the center of the inside. A diamond floor 6 made of a reinforced concrete slab which partitions the space between the steel reactor pressure vessel base 2 and the reactor pressure vessel 3 into a dry well 4 and a suppression pool 5 vertically.
【0005】このダイヤフロムフロア6の構築に際して
は図5に要部を拡大して示すように、先ず原子炉格納容
器1の建設時において鋼製原子炉圧力容器基礎台2の上
端外周と原子炉格納容器1の内周の間に、鋼製原子炉圧
力容器基礎台2からの片持ち形式の仮設支持鉄骨7を配
設し、これを支柱8により支持する。In constructing the diagram floor 6, as shown in an enlarged view of a main part in FIG. 5, first, when the reactor containment vessel 1 is constructed, the outer periphery of the upper end of the steel reactor pressure vessel base 2 and the reactor A cantilever-type temporary supporting steel frame 7 from the steel reactor pressure vessel base 2 is provided between the inner circumferences of the containment vessel 1, and is supported by a column 8.
【0006】つぎに、前記仮設支持鉄骨梁7の上面にあ
らかじめカットティー鋼を配設したシールプレート9を
据付け、その上面にスタッドボルト10と鉄筋11を配設し
た後、コンクリート12を打設して鉄筋コンクリートスラ
ブによるダイヤフロムフロア6を構築する。このダイヤ
フロムフロア6は単独で原子炉格納容器1と鋼製原子炉
圧力容器基礎台2により支持される構造となっている。Next, a seal plate 9 in which cut tee steel is previously disposed is installed on the upper surface of the temporary supporting steel beam 7, and a stud bolt 10 and a reinforcing bar 11 are disposed on the upper surface, and then concrete 12 is poured. To construct a diamond-from-floor 6 using reinforced concrete slabs. The diamond floor 6 is independently supported by the containment vessel 1 and the steel reactor pressure vessel base 2.
【0007】なお、原子炉格納容器1の内側にはライナ
プレート13が張設してあり、このライナプレート13の内
外にはライナ内側シヤプレート14とライナ外側シヤプレ
ート15が設置してある。また、打設したコンクリート12
の養生期間が終了すると、前記仮設支持鉄骨梁7および
支柱8を撤去して建設作業が完了する。[0007] A liner plate 13 is stretched inside the containment vessel 1, and a liner inner shear plate 14 and a liner outer shear plate 15 are installed inside and outside the liner plate 13. In addition, concrete 12
When the curing period is completed, the temporary supporting steel beam 7 and the support 8 are removed, and the construction work is completed.
【0008】[0008]
【発明が解決しようとする課題】ダイヤフロムフロア6
の建設工程においては、ダイヤフロムフロア6構築前に
仮設支持鉄骨梁7および支柱8を配設して、これにより
コンクリート12の打設等の構築中のダイヤフロムフロア
6を支持しており、コンクリートの養生期間の終了を持
って仮設支持鉄骨梁7等の撤去を行っていた。SUMMARY OF THE INVENTION Diamond From Floor 6
In the construction process of (1), the temporary supporting steel beams 7 and the supporting columns 8 are arranged before the construction of the diamond-from-floor 6, thereby supporting the construction of the diamond-from-floor 6 such as casting of concrete 12. At the end of the curing period, temporary supporting steel beams 7 were removed.
【0009】しかしながら、ダイヤフロムフロア6の下
部に位置するサプレッションプール5内における配管お
よびその他の設備工事は、前記ダイヤフロムフロア6に
おける仮設支持鉄骨梁7等の配設が作業の障害となり、
これらが撤去された後でなければ作業が開始できない課
題がある。However, in the piping and other facilities in the suppression pool 5 located below the diamond floor 6, the provision of the temporary support steel beams 7 and the like on the diamond floor 6 is an obstacle to the work.
There is a problem that work cannot be started until these are removed.
【0010】また、仮設支持鉄骨梁7については、原子
炉圧力容器基礎台2からの片持ち梁構造のため、鉄骨サ
イズが大きく、かつ、ダイヤフロムフロア6に設置貫通
されている逃し安全弁排気管をマンホールとの干渉によ
り、仮設支持鉄骨梁7の切り欠き等の作業が発生する課
題がある。The temporary supporting steel beam 7 has a large steel frame size because of the cantilever structure from the reactor pressure vessel base 2, and has a relief safety valve exhaust pipe which is installed and penetrated through the diamond floor 6. There is a problem that work such as notching of the temporary support steel beam 7 occurs due to interference with the manhole.
【0011】さらに、仮設支持鉄骨梁7等の撤去につい
ても、部材を搬出可能な大きさに分断する必要があり、
多大な作業量と期間を伴うばかりでなく、多量の仮設資
材を必要とする課題がある。Further, when removing the temporary supporting steel beam 7 or the like, it is necessary to divide the member into a size capable of being carried out.
There is a problem that not only requires a large amount of work and time, but also requires a large amount of temporary materials.
【0012】本発明は上記課題を解決するためになされ
たもので、鉄骨梁を原子炉圧力容器基礎台と原子炉格納
容器の両端に支持することにより、鉄骨のサイズダウン
を図り、また、ダイヤフロムフロアに設置貫通されてい
る逃し安全弁排気管貫通孔とマンホールについて鉄骨梁
との干渉を回避した配置とし、サプレッションチェンバ
内のプラットホームおよび逃し安全弁排気管サポートの
支持材として兼用することにより、鉄骨梁の撤去作業を
不要とし、ウエットウェル内の他の地域での並行作業が
可能な原子炉格納容器を提供することにある。SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems, and a steel beam is supported on both ends of a reactor pressure vessel base and a reactor containment vessel to reduce the size of a steel frame. The relief safety valve exhaust pipe through hole and manhole installed on the from floor are arranged so as to avoid interference with the steel beam, and are also used as a support in the platform in the suppression chamber and the relief safety valve exhaust pipe support. It is an object of the present invention to provide a reactor containment vessel that does not require removal work and that can be operated in parallel in other areas within the wet well.
【0013】[0013]
【課題を解決するための手段】請求項1の発明は原子炉
圧力容器と、この原子炉圧力容器を支持する原子炉圧力
容器基礎台を収容し、かつ内部を上下に区別してドライ
ウェルおよびサプレッションプールを形成するダイヤフ
ロムフロアを備えた原子炉格納容器において、前記原子
炉格納容器の内側壁面に張設されたライナプレートに設
けられた第1の鉄骨梁支持部材と、前記原子炉圧力容器
基礎台に設けられた第2の鉄骨梁支持部材と、前記第1
の鉄骨梁支持部材と前記第2の鉄骨梁支持部材間に架設
され上下方向にスリットが形成された鉄骨梁と、この鉄
骨梁上に敷設されたシールプレートと、このシールプレ
ート上に配筋された鉄筋と、前記シールプレート上に打
設されたコンクリートとを有することを特徴とする。According to the present invention, there is provided a reactor pressure vessel and a reactor pressure vessel base for supporting the reactor pressure vessel. in the containment vessel equipped with a diamond From floor to form a pool, the atomic
Installed on a liner plate stretched on the inner wall of the containment vessel
A first steel beam support member,
A second steel beam support member provided on a foundation,
Between the second steel beam support member and the second steel beam support member
Steel beams with slits formed in the vertical direction
Seal plate laid on the trabecular bone and this seal plate
Reinforcing bar placed on the plate and striking on the seal plate
And concrete provided .
【0014】[0014]
【0015】また、ダイヤフロムフロアに設置貫通され
ている逃し安全弁排気管貫通孔とマンホールについて、
鉄骨梁との干渉を回避した配置とする。さらに、サプレ
ッションチェンバ内のプラットホーム及び逃し安全弁排
気管サポートの支持材として兼用するとともに、本鉄骨
上にスタッドボルトを植設することにより、ダイヤフロ
ムフロアシールプレート上のカットティー鋼を削除す
る。これにより従来例のような仮設支持鉄骨梁の撤去が
不要となり、他の地域での並行作業が可能となり、作業
量と工期の短縮を図ることができる。[0015] Further, the relief safety valve exhaust pipe through hole and manhole which are installed and penetrated on the diamond from floor,
The layout will avoid interference with steel beams. In addition, a stud bolt is implanted on the steel frame, which serves as a support for the platform in the suppression chamber and the relief safety valve exhaust pipe support, thereby eliminating the cut tee steel on the diamond fromm floor seal plate. This eliminates the need for removing the temporary supporting steel beam as in the conventional example, enables parallel work in other areas, and can reduce the amount of work and the construction period.
【0016】[0016]
【実施例】本発明に係る原子炉格納容器の第1の実施例
について図1および図2を参照しながら説明する。図1
は、この第1の実施例に係る原子炉格納容器の要部を拡
大してして示す縦断面図で、図2は図1の要部を拡大し
て示す平面図である。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of a containment vessel according to the present invention will be described with reference to FIGS. FIG.
FIG. 2 is an enlarged longitudinal sectional view of a main part of the containment vessel according to the first embodiment, and FIG. 2 is an enlarged plan view of the main part of FIG.
【0017】すなわち、図1および図2において符号10
1 で示す原子炉格納容器の内部をドライウェル102 とサ
プレッションプール103 に区画するダイヤフロムフロア
105は、原子炉格納容器101 の内周でライナプレート104
に配設したライナ内側の鉄骨梁支持部材108 と原子炉
圧力容器基礎台106 内側の鉄骨梁支持部材109 の上端外
周との両端間に差し渡した鉄骨梁107 と、この鉄骨梁10
7 の上面に敷設したシールプレート110 上にコンクリー
ト115 を打設した鉄筋コンクリートスラブによる構成と
している。なお、符号117は基礎台縦リブである。That is, in FIG. 1 and FIG.
Diaphragm floor that divides the interior of the reactor containment vessel shown in 1 into a dry well 102 and a suppression pool 103
105 is a liner plate 104 inside the reactor containment vessel 101.
A steel beam 107 extending between both ends of a steel beam support member 108 inside the liner and a steel beam support member 109 inside the reactor pressure vessel base 106,
7 is made of a reinforced concrete slab in which concrete 115 is cast on a seal plate 110 laid on the upper surface. Reference numeral 117 is a vertical rib of the base .
【0018】原子炉格納容器101 におけるダイヤフロム
フロア105 の構築は、先ずスタッドボルト112 を植設し
たライナプレート104 および原子炉圧力容器基礎台106
を設置し、ライナプレート104 へ鉄骨支持部材108 を溶
接して配置し、また、原子炉圧力容器基礎台106 側に
も、鉄骨支持部材109 を溶接して配置する。The construction of the diamond floor 105 in the containment vessel 101 is performed by firstly forming a liner plate 104 on which stud bolts 112 are implanted and a reactor pressure vessel base 106.
The steel frame support member 108 is welded to the liner plate 104, and the steel frame support member 109 is also welded to the reactor pressure vessel base 106 side.
【0019】つぎに、この鉄骨支持部材108 ,109 との
間に、複数本の鉄骨梁107 を設置する。この鉄骨梁107
にはサプレッションプールプラットホーム113 および逃
し安全弁排気管サポート114 が一体化されている。Next, a plurality of steel beams 107 are installed between the steel support members 108,109. This steel beam 107
, A suppression pool platform 113 and a relief safety valve exhaust pipe support 114 are integrated.
【0020】この後、鉄骨梁107 上にスタッドボルト11
1 を植設し、鉄骨梁107 間の上面にシールプレート110
を敷設する。シールプレート110 上に鉄筋116 の配筋を
して、コンクリート115 を打設し養生期間を経過してダ
イヤフロムフロア105 が完成する。Thereafter, the stud bolt 11 is placed on the steel beam 107.
1 and plant a seal plate 110 on the upper surface between the steel beams 107.
Laying. Reinforcing bars 116 are arranged on the seal plate 110, concrete 115 is poured, and after the curing period, the diamond fromm floor 105 is completed.
【0021】なお、鉄骨梁107 は、ダイヤフロムフロア
105 構築時のコンクリート打設荷重およびシールプレー
ト自重を受け持つ構造となっており、さらに、サプレッ
ションプラットホーム113 、逃し安全弁排気管サポート
114 の荷重を受け持つ構造となっている。The steel beam 107 is a diamond-from-floor.
105 The structure is designed to bear the concrete placing load and seal plate weight at the time of construction. In addition, the suppression platform 113, relief safety valve exhaust pipe support
It is designed to handle 114 loads.
【0022】この実施例によれば、ダイヤフロムフロア
105 の構築時に、原子炉格納容器101 がダイヤフロムフ
ロア105 のレベルまで完成していることにより、ダイヤ
フロムフロア105 構築時のコンクリート115 の打設荷重
等の支持部材を、原子炉圧力容器の基礎台106 と原子炉
格納容器101 の両端に支持することが可能となる。した
がって、従来の片持ち形式に対して、鉄骨サイズのサイ
ズダウンおよび支柱の削除が可能となる効果がある。According to this embodiment, the diamond-from floor
When the reactor containment vessel 101 was completed to the level of the diamond fromm floor 105 at the time of the construction of the 105, the supporting members such as the concrete 115 casting load at the time of the construction of the diamond fromm floor 105 could be used as the base of the reactor pressure vessel. It can be supported at both ends of the table 106 and the containment vessel 101. Therefore, there is an effect that the size of the steel frame can be reduced and the columns can be deleted as compared with the conventional cantilever type.
【0023】また、従来例ではダイヤフロムフロア構築
後、支持鉄骨梁、支柱を撤去していたが、この実施例に
よればダイヤフロムフロア構築後もサプレッションプー
ルプラットホーム113 および逃し安全弁排気管サポート
114の支持材として、鉄骨梁107 を利用することによ
り、仮設支持梁撤去工事が不要となり、資材と作業工程
が削減されると共に、サプレッションプール103 内の他
の地域における作業に支障を与えず、並行作業が行えて
工程が短縮できる効果がある。In the conventional example, the supporting steel beams and the columns are removed after the construction of the diagram floor, but according to this embodiment, even after the construction of the diagram from floor, the suppression pool platform 113 and the relief safety valve exhaust pipe support are removed.
As 114 support of, by utilizing a steel beam 107, the temporary setting support beams dismantling is not required, the materials and working steps is reduced, without giving any trouble to operations in other parts of the suppression pool 103 In addition, there is an effect that the processes can be shortened by performing parallel operations.
【0024】さらに、従来例では、シールプレート上に
カットティー鋼を設け、カットティー鋼上のスタッドボ
ルトの引抜き荷重等を線荷重にならしていたが、この実
施例によれば鉄骨梁上にスダッドボルトを設けることに
よってカットティー鋼を削除できる効果がある。Further, in the conventional example, cut-tee steel is provided on the seal plate, and the pull-out load and the like of the stud bolt on the cut-tee steel are made equal to the linear load. By providing the Sudd bolt, there is an effect that the cut tee steel can be deleted.
【0025】次に図3により本発明に係る原子炉格納容
器の第2の実施例を説明する。図3においては図1と同
一部分に同一符号を付して、重複する部分の説明を省略
することにする。Next, a second embodiment of the containment vessel according to the present invention will be described with reference to FIG. In FIG. 3, the same portions as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping portions will be omitted.
【0026】この第2の実施例が前記第1の実施例と異
なる点は鉄骨梁107 に1カ所以上のスリット121 を設け
たことにあり、その他の部分は第1の実施例と同様であ
る。この第2の実施例によれば鉄骨梁107 の熱膨張を防
止することができる。なお、その他の部分は第1の実施
例と同様の作用効果が得られる。The second embodiment differs from the first embodiment in that one or more slits 121 are provided in the steel beam 107, and the other parts are the same as in the first embodiment. . According to the second embodiment, the thermal expansion of the steel beam 107 can be prevented. The other parts have the same functions and effects as those of the first embodiment.
【0027】また、図3に示したスリット121 の代りに
部分的にボルトで接合した鉄骨梁とすることができ、こ
の場合にはスリット121 を撤去することもでき、さら
に、鉄骨梁上にスタッドを設置しない支持鉄骨を使用す
ることもできる。Further, instead of the slit 121 shown in FIG. 3, a steel beam partially connected by bolts can be used. In this case, the slit 121 can be removed, and further, a stud is provided on the steel beam. It is also possible to use a supporting steel frame without installing.
【0028】上述した各実施例において、鉄骨梁107 の
配置に関して原子炉圧力容器基礎台106 の縦リブ位置と
鉄骨梁107 の位置を合わせることにより基礎台の強度を
確保できる。また、ダイヤフロムフロアに設置貫通され
ている逃し安全弁排気管貫通孔とマンホールについて、
鉄骨梁との干渉を回避した配置とする。In each of the above-described embodiments, the strength of the steel base 107 can be ensured by aligning the position of the vertical ribs of the reactor pressure vessel base 106 with the position of the steel base 107 for the arrangement of the steel base 107. In addition, the relief safety valve exhaust pipe through hole and manhole that are installed and penetrated on the diamond from floor,
The layout will avoid interference with steel beams.
【0029】さらに、鉄骨梁107 について、プール水を
収容するウエットウェル内のプラットホームおよび逃し
安全弁排気管サポートの支持材として兼用し、従来の仮
設鉄骨梁を撤去不要とする。Further, the steel beam 107 is also used as a platform in the wet well for accommodating the pool water and as a support for the relief pipe of the relief safety valve, so that the conventional temporary steel beam need not be removed.
【0030】[0030]
【発明の効果】本発明によれば、ダイヤフロムフロアの
建設工程において、鉄骨サイズのサイズダウンおよび支
柱の削除が可能となり、また、仮設鉄骨梁の撤去作業が
削除され、建設工程および資材を低減できる効果があ
る。According to the present invention, it is possible to reduce the size of the steel frame and to remove the columns in the construction process of the diamond-from-floor, and to eliminate the work of removing the temporary steel beam, thereby reducing the construction process and materials. There is an effect that can be done.
【図1】本発明に係る原子炉格納容器の第1の実施例の
ダイヤフロムフロア要部を拡大して示す縦断面図。FIG. 1 is an enlarged longitudinal sectional view showing a main part of a diagram from floor of a first embodiment of a reactor containment vessel according to the present invention.
【図2】図1における要部を拡大して示す平面図。FIG. 2 is an enlarged plan view showing a main part in FIG. 1;
【図3】本発明に係る原子炉格納容器の第2の実施例の
要部拡大縦断面図。FIG. 3 is an enlarged longitudinal sectional view of a main part of a second embodiment of the containment vessel according to the present invention.
【図4】従来の原子炉格納容器を一部側面で示す縦断面
図。FIG. 4 is a longitudinal sectional view showing a conventional reactor containment vessel with a partial side view.
【図5】図4に示した原子炉格納容器におけるダイヤフ
ロムフロアの要部を拡大して示す縦断面図。FIG. 5 is an enlarged longitudinal sectional view showing a main part of a diagram floor in the containment vessel shown in FIG. 4;
1,101 …原子炉格納容器、4,102 …ドライウェル、
5,103 …サプレッションプール、13,104 …ライナプ
レート、6,105 …ダイヤフロムフロア、2,106 …原
子炉圧力容器基礎台、7,107 …鉄骨梁、 108…鉄骨梁
支持部材(ライナ)、 109…鉄骨梁支持部材(基礎台)
9,110 …シールプレート、10,111 …スタッドボルト
(シールプレート)、 112…スタッドボルト(ライ
ナ)、 113…サプレッションプラットホーム、 114…逃
し安全弁排気管サポート、12,115 …コンクリート、1
1,116 …鉄筋、 117…基礎台縦リブ、 118…鉄骨小
梁、 119…逃し安全弁排気管貫通孔、 120…マンホー
ル、3…原子炉圧力容器、8…支柱、14…ライナ内側シ
ヤプレート、15…ライナ外側シヤプレート、121 …スリ
ット。1,101 ... containment containment vessel, 4,102 ... dry well,
5,103 ... suppression pool, 13,104 ... liner plate, 6,105 ... diaphragm floor, 2,106 ... reactor pressure vessel base, 7,107 ... steel beam, 108 ... steel beam support member (liner), 109… Steel beam support member (foundation)
9,110 ... seal plate, 10, 111 ... stud bolt (seal plate), 112 ... stud bolt (liner), 113 ... suppression platform, 114 ... relief safety valve exhaust pipe support, 12, 115 ... concrete, 1
1,116… Reinforcing bar, 117… Vertical rib of base, 118… Steel beam, 119… Thru-hole of relief valve exhaust pipe, 120… Manhole, 3… Reactor pressure vessel, 8… Strut, 14… Shear plate inside liner, 15 ... Liner outer shear plate, 121 ... Slit.
フロントページの続き (56)参考文献 特開 平7−234296(JP,A) 実開 平6−64195(JP,U) 実開 平6−4696(JP,U) 実開 平6−72095(JP,U) (58)調査した分野(Int.Cl.7,DB名) G21C 13/02 G21C 13/00 Continuation of the front page (56) References JP-A-7-234296 (JP, A) JP-A-6-64195 (JP, U) JP-A-6-4696 (JP, U) JP-A-6-72095 (JP, U) , U) (58) Fields investigated (Int. Cl. 7 , DB name) G21C 13/02 G21C 13/00
Claims (1)
を支持する原子炉圧力容器基礎台を収容し、かつ内部を
上下に区別してドライウェルおよびサプレッションプー
ルを形成するダイヤフロムフロアを備えた原子炉格納容
器において、前記原子炉格納容器の内側壁面に張設され
たライナプレートに設けられた第1の鉄骨梁支持部材
と、前記原子炉圧力容器基礎台に設けられた第2の鉄骨
梁支持部材と、前記第1の鉄骨梁支持部材と前記第2の
鉄骨梁支持部材間に架設され上下方向にスリットが形成
された鉄骨梁と、この鉄骨梁上に敷設されたシールプレ
ートと、このシールプレート上に配筋された鉄筋と、前
記シールプレート上に打設されたコンクリートとを有す
ることを特徴とする原子炉格納容器。1. A reactor pressure vessel, comprising: a reactor pressure vessel base for supporting the reactor pressure vessel; and a diagram from which the inside is vertically separated to form a drywell and a suppression pool. In the containment vessel, a first steel beam support member provided on a liner plate stretched on an inner wall surface of the containment vessel, and a second steel beam provided on the reactor pressure vessel base A support member, a steel beam erected between the first steel beam support member and the second steel beam support member and having a slit formed in a vertical direction, a seal plate laid on the steel beam, A containment vessel comprising: a reinforcing bar arranged on a seal plate; and concrete cast on the seal plate.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP31620794A JP3340871B2 (en) | 1994-12-20 | 1994-12-20 | Reactor containment vessel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP31620794A JP3340871B2 (en) | 1994-12-20 | 1994-12-20 | Reactor containment vessel |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH08179076A JPH08179076A (en) | 1996-07-12 |
JP3340871B2 true JP3340871B2 (en) | 2002-11-05 |
Family
ID=18074498
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP31620794A Expired - Lifetime JP3340871B2 (en) | 1994-12-20 | 1994-12-20 | Reactor containment vessel |
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Country | Link |
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JP (1) | JP3340871B2 (en) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP5003253B2 (en) * | 2007-04-04 | 2012-08-15 | 鹿島建設株式会社 | RC beam construction method |
US7685923B1 (en) * | 2008-08-27 | 2010-03-30 | Sandia Corporation | Fragment capture device |
JP6539105B2 (en) * | 2015-05-11 | 2019-07-03 | 日立Geニュークリア・エナジー株式会社 | Reactor building |
-
1994
- 1994-12-20 JP JP31620794A patent/JP3340871B2/en not_active Expired - Lifetime
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JPH08179076A (en) | 1996-07-12 |
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