JPS63186185A - Support structure of nuclear-reactor pressure vessel - Google Patents
Support structure of nuclear-reactor pressure vesselInfo
- Publication number
- JPS63186185A JPS63186185A JP62016157A JP1615787A JPS63186185A JP S63186185 A JPS63186185 A JP S63186185A JP 62016157 A JP62016157 A JP 62016157A JP 1615787 A JP1615787 A JP 1615787A JP S63186185 A JPS63186185 A JP S63186185A
- Authority
- JP
- Japan
- Prior art keywords
- pressure vessel
- reactor pressure
- reinforcing ribs
- support structure
- bracket
- 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.)
- Granted
Links
- 230000003014 reinforcing effect Effects 0.000 claims description 34
- 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 claims description 21
- 239000004567 concrete Substances 0.000 claims description 5
- 230000002093 peripheral effect Effects 0.000 claims 1
- 238000001816 cooling Methods 0.000 description 14
- 238000007689 inspection Methods 0.000 description 5
- 230000001629 suppression Effects 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 238000012423 maintenance Methods 0.000 description 4
- 239000011810 insulating material Substances 0.000 description 3
- 239000011150 reinforced concrete Substances 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000000737 periodic effect Effects 0.000 description 2
- 230000002787 reinforcement Effects 0.000 description 2
- OWNRRUFOJXFKCU-UHFFFAOYSA-N Bromadiolone Chemical compound C=1C=C(C=2C=CC(Br)=CC=2)C=CC=1C(O)CC(C=1C(OC2=CC=CC=C2C=1O)=O)C1=CC=CC=C1 OWNRRUFOJXFKCU-UHFFFAOYSA-N 0.000 description 1
- 101100334009 Caenorhabditis elegans rib-2 gene Proteins 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000012774 insulation material Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000003020 moisturizing 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Pressure Vessels And Lids Thereof (AREA)
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】
（°発明の目的）
（産業上の利用分野）
本発明は原子炉格納容器内に収納される原子炉圧力容器
の支持構造に係り、特に原子炉圧力容器を支持する原子
炉圧力容器支持ペデスタルのブラケット受け部の改良構
造に関する。[Detailed Description of the Invention] (°Objective of the Invention) (Industrial Application Field) The present invention relates to a support structure for a reactor pressure vessel housed in a nuclear reactor containment vessel, and in particular to a support structure for a reactor pressure vessel housed in a nuclear reactor containment vessel. This invention relates to an improved structure of a bracket receiving part of a reactor pressure vessel support pedestal.
（従来の技術）
沸騰水増原子炉等の軽“水戸は第５図に示すように構成
され、原子炉格納容器１内に原子炉圧力容器２が収納さ
れ、この原子炉圧力容器２は原子炉圧力容器支持ペデス
タル３の上部に据付けられる。(Prior art) A light "mito" such as a boiling water reactor is constructed as shown in FIG. It is installed on the top of the reactor pressure vessel support pedestal 3.
原子炉格納容器１は鉄筋コンクリート１ａの内側にライ
ナ１ｂを張った鉄筋コンクリート製格納容器であり、上
記原子炉格納容器１の中央部には原子炉圧力容器支持ペ
デスタル３が突設される。The reactor containment vessel 1 is a reinforced concrete containment vessel in which a liner 1b is stretched inside the reinforced concrete 1a, and a reactor pressure vessel support pedestal 3 is protruded from the center of the reactor containment vessel 1.
この原子炉圧力容器支持ペデスタル３上に原子炉圧力容
器２を囲む筒状の原子炉熱遮蔽壁４が突設されている。A cylindrical reactor heat shielding wall 4 that surrounds the reactor pressure vessel 2 projects from the reactor pressure vessel support pedestal 3 .
上記原子炉圧力容器支持ペデスタル３の上部内周壁には
ブラケット部５が一体に形成されており、このブラケッ
ト部５に原子炉圧力容器の支持スカート６が据付けられ
、原子炉圧力容器２からの荷重を直接受けている。上記
ブラケット部５はプラケット受け部７で下側から補強さ
れる。A bracket part 5 is integrally formed on the upper inner circumferential wall of the reactor pressure vessel support pedestal 3, and a support skirt 6 for the reactor pressure vessel is installed on this bracket part 5. are receiving it directly. The bracket part 5 is reinforced from below by a placket receiving part 7.
ブラケット受け部７は、第６図および第７図に示ずよう
に、原子炉圧力容器支持ペデスタル３の内周側に設けら
れた補強リブ７ａを備え、この補強リブ７ａの先端にシ
ェルプレート７ｂが固定される。補強リブ７ａは原子炉
圧力容器支持へデスタル３の周方向に間隔をおいて全体
として放射状に設けられ、上記支持ペデスタル３と補強
リブ７ａとシェルプレート７ｂとで囲まれた空間にコン
クリート７Ｃが充填される。As shown in FIGS. 6 and 7, the bracket receiving portion 7 includes a reinforcing rib 7a provided on the inner circumferential side of the reactor pressure vessel support pedestal 3, and a shell plate 7b at the tip of the reinforcing rib 7a. is fixed. The reinforcing ribs 7a are provided radially as a whole at intervals in the circumferential direction of the destal 3 to support the reactor pressure vessel, and the space surrounded by the supporting pedestal 3, the reinforcing ribs 7a, and the shell plate 7b is filled with concrete 7C. be done.
一方、ブラケット受け部７と原子炉圧力容器２の保温材
８との間には原子炉内循環ポンプとしてのインターナル
ポンプを冷却する熱交換器９が配置されている。On the other hand, a heat exchanger 9 is arranged between the bracket receiving part 7 and the heat insulating material 8 of the reactor pressure vessel 2 to cool an internal pump serving as a circulation pump in the reactor.
（発明が解決しようとする問題点）
従来の原子炉圧力容器の支持構造においては、ブラケッ
ト部５を補強するブラケット受け部７と原子炉圧力容器
２の保温材８との間にインターナルポンプ冷却用熱交換
器９が配置されているが、配置スペースが狭いため、熱
交換器９の上部とブラケット受け部７とのクリアランス
や上記熱交換器９と原子炉圧力容器２の保湿材８とのク
リアランスが充分にとれず、またアクセス性が悪い等の
問題があった。(Problems to be Solved by the Invention) In the conventional support structure for a reactor pressure vessel, internal pump cooling is provided between the bracket receiving part 7 that reinforces the bracket part 5 and the heat insulating material 8 of the reactor pressure vessel 2. A heat exchanger 9 for use in the reactor is installed, but because the installation space is narrow, the clearance between the upper part of the heat exchanger 9 and the bracket receiving part 7, and the clearance between the heat exchanger 9 and the moisturizing material 8 of the reactor pressure vessel 2 are limited. There were problems such as insufficient clearance and poor accessibility.
また、インターナルポンプ冷却用熱交換器９は定検時に
内蔵されている熱交換チューブが引き扱かれるが、上記
熱交換器９の下方には一部の熱交換器を除いて制御棒駆
動機槙配管（以下ＣＲＤ配管という。）１０が設けられ
ている。このＣＲＤ配管１０の存在により熱交換器９の
下方に充分なスペースを確保することができず、定検的
熱交換器の保守点検作業の作業性が悪く、困難であった
。In addition, the built-in heat exchange tubes of the internal pump cooling heat exchanger 9 are handled during regular inspections, but the control rod drive unit is located below the heat exchanger 9 except for some heat exchangers. Maki piping (hereinafter referred to as CRD piping) 10 is provided. Due to the presence of the CRD piping 10, it was not possible to secure a sufficient space below the heat exchanger 9, making it difficult to perform periodic maintenance and inspection of the heat exchanger.
本発明は上述した事情を考慮してなされたもので、イン
ターナルポンプ冷却用熱交換器等の機器の配置性やアク
セス性を向上させ、機器の保守点検作業を容易にし、メ
ンテナンス性を向上させた原子炉圧力容器の支持構造を
提供することを目的とする。The present invention has been made in consideration of the above-mentioned circumstances, and improves the ease of arrangement and accessibility of equipment such as internal pump cooling heat exchangers, facilitates maintenance and inspection of equipment, and improves maintainability. The purpose is to provide a support structure for a nuclear reactor pressure vessel.
（問題点を解決するための手段）
本発明は、原子炉格納容器内に原子炉圧力容器を収納し
、この原子炉圧力容器を原子炉圧力容器支持ペデスタル
の上部に据付けた原子炉圧力客器の支持構造において、
上記原子炉圧力容器の荷重を受けるブラケッ］・部の下
側に補強リブを放射状に設け、上記補強リブでブラケッ
ト部を補強するブラケッ］・受け部を構成したものであ
る。(Means for Solving the Problems) The present invention provides a reactor pressure passenger equipment in which a reactor pressure vessel is housed in a reactor containment vessel, and this reactor pressure vessel is installed on the upper part of a reactor pressure vessel support pedestal. In the support structure of
Reinforcing ribs are radially provided on the lower side of the bracket that receives the load of the reactor pressure vessel, and the bracket is reinforced with the reinforcing ribs to form a receiving part.
、 （・作用）
この原子炉圧力容器の支持構造は、原子炉圧力容器の荷
重を受けるブラケット部の下側に補強リブを放射状に設
け、上記補強リブでブラケット部を補強するブラケット
受け部を形成したから、ブラケット受け部は補強リブ間
に空隙が形成される。この空隙を積極的に利用し、イン
ターナルポンプ冷却用熱交換器等の機器配置スペースと
して活用することができ、これにより、様器の配置性や
ア・クセス性を向上させ、機器の保守点検作業やメンテ
ナンス性を容易にしたものである。(・Function) This reactor pressure vessel support structure has reinforcing ribs radially provided on the lower side of the bracket part that receives the load of the reactor pressure vessel, and the reinforcing ribs form a bracket receiving part that reinforces the bracket part. Therefore, a gap is formed between the reinforcing ribs in the bracket receiving portion. This gap can be actively utilized as a space for arranging equipment such as heat exchangers for cooling internal pumps. This makes work and maintenance easier.
（実施例）
以下、本発明に′係る原子炉圧力容器の支持構造につい
て添付図面を参照して説明する。(Example) Hereinafter, a support structure for a nuclear reactor pressure vessel according to the present invention will be described with reference to the accompanying drawings.
第１図は軽水炉としての沸騰水型原子炉を示し、この原
子炉は原子炉格納容器１１内に原子炉圧力容器１２が収
納される。原子炉圧ツノ容器１２は円筒状の原子炉熱遮
蔽壁１３で囲まれる一方、原子炉圧力容器支持ペデスタ
ル１４の上部に据付けられる。原子炉圧力容器支持ペデ
スタル１４は原子炉格納容器１１内の中央部に立設され
る。原子炉格納容器１１は鉄筋コンクリート壁１１ａの
内側にライナ１１ｂを内張すしたもので、その内部は原
子炉圧力容器支持ペデスタル１４とダイヤフラムフロア
１５によりサプレッションプール水１６を貯溜したサプ
レッションチャンバ１７、下部ドライウェル部１８およ
び上部ドライウェル部１９に区分けされる。FIG. 1 shows a boiling water reactor as a light water reactor, in which a reactor pressure vessel 12 is housed within a reactor containment vessel 11. The reactor pressure vessel 12 is surrounded by a cylindrical reactor heat shielding wall 13 and is installed on the top of a reactor pressure vessel support pedestal 14 . The reactor pressure vessel support pedestal 14 is erected at the center of the reactor containment vessel 11 . The reactor containment vessel 11 has a reinforced concrete wall 11a lined with a liner 11b, and the inside contains a suppression chamber 17 in which suppression pool water 16 is stored using a reactor pressure vessel support pedestal 14 and a diaphragm floor 15, and a lower dry chamber. It is divided into a well part 18 and an upper dry well part 19.
一方、原子炉圧力容器支持ペデスタル１４の上部内周壁
側には、原子炉圧力容器１２の荷重を受けるブラケット
部２０が一体に設けられる。ブラケット部２０は第２図
および第３図に示すように原子炉圧力容器支持ペデスタ
ル１４の内周に沿って周方向に形成され、このブラケッ
ト部２０上に原子炉圧力容器１２の支持スカート２１を
据付けるようになっている。On the other hand, a bracket portion 20 that receives the load of the reactor pressure vessel 12 is integrally provided on the upper inner circumferential wall side of the reactor pressure vessel support pedestal 14 . As shown in FIGS. 2 and 3, the bracket part 20 is formed in the circumferential direction along the inner circumference of the reactor pressure vessel support pedestal 14, and the support skirt 21 of the reactor pressure vessel 12 is mounted on the bracket part 20. It is ready to be installed.
上記ブラケット部２０はその下方に設けられたブラケッ
ト受け部２２で補強される。ブラケット受け部２２は原
子炉圧力容器支持ペデスタル１４と一体あるいは一体的
に設けられた補強リブ２５から構成される。補強リブ２
５は原子炉圧力容器支持ペデスタル１４の内周壁に沿っ
て周方向に間隔をおいて設置された縦リブであり、全体
として放射状に配設される。The bracket portion 20 is reinforced by a bracket receiving portion 22 provided below. The bracket receiving portion 22 is composed of reinforcing ribs 25 that are integrally or integrally provided with the reactor pressure vessel support pedestal 14 . Reinforcement rib 2
Reference numeral 5 denotes vertical ribs installed along the inner circumferential wall of the reactor pressure vessel support pedestal 14 at intervals in the circumferential direction, and are arranged radially as a whole.
補強リブ２５はトーラス状ブラケット部２０の横幅（半
径方向の幅）全面にわたって支持する大きさ、形状に成
形され、この支持構造によりブラケット部２０の高さを
従来のブラケット部より小さくすることができる。The reinforcing rib 25 is shaped and sized to support the entire width (radial width) of the torus-shaped bracket portion 20, and this support structure allows the height of the bracket portion 20 to be smaller than that of conventional bracket portions. .
また１、ブラケット受け部２２は放射状に配設された補
強リブ２５のみで構成され、補強り・ブ２５゜２５間に
空間２６が形成される。この空＠２６は原子炉圧力容器
支持ペデスタル１４と原子炉圧力容器１２の保温材２７
とにより画成され、機器配置スペースとして活用される
。Further, 1. The bracket receiving portion 22 is composed only of reinforcing ribs 25 arranged radially, and a space 26 is formed between the reinforcing ribs 25°25. This space @26 is the heat insulating material 27 of the reactor pressure vessel support pedestal 14 and the reactor pressure vessel 12.
The space is defined by the space and used as equipment placement space.
機器配置スペース２６にはインターナルポンプ冷却用熱
交換器２８等の必要な機器が収納され、設置される。ブ
ラケット受°け部２２を補強リブ２５のみで構成するこ
とにより、シェルプレートを削除でき、従来のようにシ
ェルプレートの外側にコンクリートを充填させる必要が
ないので、ブラケット部２０の下方に大きな空間（クリ
アランス）２６を確保でき、この空間２６・をインター
ナルポンプ冷却用熱交換器２８等の機器配置スペースに
利用できる。したがって、インターナルポンプ冷却用熱
交換器２８の配置性が向上する一方、ブラケット受け廊
付近に上記熱交換器２８へのアクセススペースを広くと
ることができ、アクセス性が改善され、向上する。Necessary equipment such as an internal pump cooling heat exchanger 28 is housed and installed in the equipment arrangement space 26. By configuring the bracket receiving part 22 only with the reinforcing ribs 25, the shell plate can be removed and there is no need to fill the outside of the shell plate with concrete as in the conventional case, so a large space ( Clearance) 26 can be secured, and this space 26 can be used as a space for arranging equipment such as an internal pump cooling heat exchanger 28. Therefore, the arrangement of the internal pump cooling heat exchanger 28 is improved, and a wider access space to the heat exchanger 28 can be secured near the bracket receiving gallery, thereby improving the accessibility.
前記サプレッションチャンバ１７には原子炉格納容器１
１の外部から下部ドライウェル部１８へアクセスするた
めのトンネル２９が設けられており、このトンネル２９
内の上方にはＣＲＤ配管３０が通されている。The suppression chamber 17 includes the reactor containment vessel 1.
A tunnel 29 is provided for accessing the lower dry well section 18 from the outside of the dry well section 1.
A CRD pipe 30 is passed above the inside.
この原子炉圧力容器１２の支持構造においては、ブラケ
ット部２０を補強するブラケット受け部２２を、第１図
ないし第３図に示すように補強リブ２５のみで構成し、
原子炉圧力容器支持ペデスタル１４の内筒や補強リブ２
５で囲まれた空間２６をインターナルポンプ冷却用熱交
換器２８等の機器配置スペースとして活用したので、イ
ンターナルポンプ冷却用熱交換器２８廻りが広くなり、
機器配置性が向上するとともにアクセススペースも広く
とれ、機器へのアクセス性も向上する。In this support structure for the reactor pressure vessel 12, the bracket receiving part 22 that reinforces the bracket part 20 is composed only of reinforcing ribs 25 as shown in FIGS. 1 to 3,
Inner cylinder and reinforcing ribs 2 of the reactor pressure vessel support pedestal 14
Since the space 26 surrounded by 5 is used as a space for arranging equipment such as the internal pump cooling heat exchanger 28, the area around the internal pump cooling heat exchanger 28 becomes wider.
Equipment placement is improved, access space is also wider, and equipment accessibility is also improved.
また、補強リブ２５のサイズ（リブ幅およびリプの高さ
）を大きくし、補強リブ２５でブラケット部２０の下面
全幅を支持するようにしたから、ブラケット部２０の高
さを小さくすることができ、その分だけインターナルポ
ンプ冷却用熱交換器２８の設置ポジションを上方に上げ
ることができる。Furthermore, since the size of the reinforcing ribs 25 (rib width and lip height) is increased so that the entire width of the lower surface of the bracket part 20 is supported by the reinforcing ribs 25, the height of the bracket part 20 can be reduced. , the installation position of the internal pump cooling heat exchanger 28 can be raised upward by that amount.
その結果、インターナルポンプ冷却用熱交換器２８とＣ
ＲＤ配管３０との間に形成される熱交換チューブの引扱
きスペースを充分に確保することかでき、定検時の作業
性やメンテナンス性が向上する。As a result, the internal pump cooling heat exchanger 28 and C
A sufficient space for handling the heat exchange tube formed between the heat exchange tube and the RD pipe 30 can be secured, and workability and maintainability during periodic inspections are improved.
また、ブラケット受け部２２を補強リブ２５のみで構成
し、シェルプレートが不要なブラケット部補強構造とし
たので、シェルプレート分鋼相聞を削減することができ
、コストダウンを図ることができる。In addition, since the bracket receiving portion 22 is constructed of only the reinforcing ribs 25, and the bracket portion is reinforced with no shell plate, it is possible to reduce the number of shell plate parts and reduce costs.
第４図は原子炉圧力容器の支持構造の変形例を示すもの
である。FIG. 4 shows a modification of the support structure of the reactor pressure vessel.
この変形例に示された原子炉圧力容器の支持構造が第１
図ないし第３図に示された支持構造と基本的に相違する
点は、補強リブ２５間に形成される空間２６のうち、イ
ンターナルポンプ冷却用熱交換器２８等の機器が配置さ
れない区域には、シェルプレート３３を設け、このシェ
ルプレート３３と補強リブ２５．２５とで囲まれた領域
にコ・ンクリート３４を充填させ、ブラケット受け部２
２Ａの剛性を向上させたものである。The support structure of the reactor pressure vessel shown in this modification is the first
The basic difference from the support structure shown in FIGS. 3 to 3 is that in the space 26 formed between the reinforcing ribs 25, the area where equipment such as the internal pump cooling heat exchanger 28 is not placed is The shell plate 33 is provided, and the area surrounded by the shell plate 33 and the reinforcing ribs 25.25 is filled with concrete 34, and the bracket receiving portion 2 is
2A with improved rigidity.
この場合にも、第１実施例で示された原子炉圧力容器の
支持構造と同様な効果が得られる。In this case as well, the same effects as the support structure for the reactor pressure vessel shown in the first embodiment can be obtained.
以上に述べたように本発明に係る原子炉圧力容器の支持
構造においては、原子炉圧力容器の荷重を受けるブラケ
ット部の下側に補強リブを放射状に設け、この補強リブ
でブラケット部を補強するブラケット受け部を構成した
から、補強リブ間の空間をインターナルポンプ冷却用熱
交換器等の機器配置スペースとして活用することができ
、上記熱交換器等の機器廻りのスペースを広くとること
ができ、機器の配置性や機器へのアクセス性が向上する
とともに、機器の保守点検作業性の向上を図ることがで
き、機器のメンテナンス性が改善される。As described above, in the reactor pressure vessel support structure according to the present invention, reinforcing ribs are provided radially below the bracket part that receives the load of the reactor pressure vessel, and the bracket part is reinforced with the reinforcing ribs. Since the bracket receiving part is configured, the space between the reinforcing ribs can be used as a space for arranging equipment such as the heat exchanger for cooling the internal pump, and the space around the equipment such as the heat exchanger can be expanded. In addition to improving the arrangement of the equipment and the accessibility to the equipment, it is possible to improve the ease of maintenance and inspection of the equipment, and the maintainability of the equipment is improved.
第１図は本発明に係る原子炉圧力容器の支持構造の−、
実施例を示す断面図、第２図は第１図のＢ部を拡大して
示す部分的縦断面図、第３図は第２図の■−■線に沿う
部分的平断面図、第４図は本発明に・係る原子炉圧力容
器の支持構造の変形例を示す図、第５図は従来の原子炉
圧力容器の支持構造を示す断面図、第６図は第５図のＡ
部を拡大して示す部分的縦断面図、第７図は第６図の■
−■線に沿う平断面図である。
１１・・・原子炉格納容器、１２・・・原子炉圧力容器
、１３・・・原子炉熱遮蔽壁、１４・・・原子炉圧力容
器支持ペデスタル、１５・・・ダイヤフラムフロア、１
６・・・サプレッションブール水、１７・工・サプレッ
ションチャンバ、１８・・・下部ドライウェル部、１９
・・・上部ドライウェル部、２０・・・ブラケット部、
２１・・・支持スカート、２２．２２Ａ・・・ブラケッ
ト受け部、２５・・・補強リブ、２６・・・空間（機器
配置スペース）、２７・・・保温材、２．８・・・イン
ターナルポンプ冷却用熱交換器、２９−、・・トンネル
、３０・・・ＣＲＤ配管、３３・・・シェルプレート、
３４・・・コンクリート。
出願人代理人 波 多 野 久第２図
第３図
円
第４図
第６図
第７図FIG. 1 shows a support structure for a reactor pressure vessel according to the present invention.
FIG. 2 is a partial vertical sectional view showing an enlarged section B of FIG. 1, FIG. 3 is a partial plan sectional view taken along the line The figure shows a modified example of the support structure for a reactor pressure vessel according to the present invention, FIG. 5 is a sectional view showing a conventional support structure for a reactor pressure vessel, and FIG. 6 is A of FIG.
Fig. 7 is a partial vertical cross-sectional view showing an enlarged view of the part shown in Fig. 6.
It is a plane cross-sectional view along the -■ line. DESCRIPTION OF SYMBOLS 11... Reactor containment vessel, 12... Reactor pressure vessel, 13... Reactor heat shielding wall, 14... Reactor pressure vessel support pedestal, 15... Diaphragm floor, 1
6... Suppression boule water, 17. Engineering/suppression chamber, 18... Lower dry well section, 19
... Upper dry well part, 20... Bracket part,
21...Support skirt, 22.22A...Bracket receiving part, 25...Reinforcement rib, 26...Space (equipment placement space), 27...Heat insulation material, 2.8...Internal Pump cooling heat exchanger, 29-,... tunnel, 30... CRD piping, 33... shell plate,
34...Concrete. Applicant's agent Hisashi Hatano Figure 2 Figure 3 Circle Figure 4 Figure 6 Figure 7
Claims (1)
原子炉圧力容器を原子炉圧力容器支持ペデスタルの上部
に据付けた原子炉圧力容器の支持構造において、上記原
子炉圧力容器の荷重を受けるブラケット部の下側に補強
リブを放射状に設け、上記補強リブでブラケット部を補
強するブラケット受け部を構成したことを特徴とする原
子炉圧力容器の支持構造。 ２、ブラケット部は原子炉圧力容器支持ペデスタルの上
部内周側に一体に設けられ、上記ブラケットを補強する
補強リブは放射方向に間隔をおいて配設された縦リブで
ある特許請求の範囲第１項に記載の原子炉圧力容器の支
持構造。 ３、補強リブは隣り合う補強リブとの間に空間が形成さ
れ、この空間を機器配置スペースに設定した特許請求の
範囲１項に記載の原子炉圧力容器の支持構造。 ４、補強リブはブラケット部の幅全体を支持する大きさ
、形状に形成され、ブラケット部の高さを小さくした特
許請求の範囲第１項に記載の原子炉圧力容器の支持構造
。 ５、補強リブ間に形成される空間のうち、機器配置に利
用しない空間の補強リブ間にシェルプレートを設け、こ
のシェルプレートと補強リブ、原子炉圧力容器支持ペデ
スタルで囲まれた部分にコンクリートを充填してなる特
許請求の範囲第１項に記載の原子炉圧力容器の支持構造
。[Claims] 1. In a support structure for a reactor pressure vessel in which a reactor pressure vessel is housed in a reactor containment vessel and this reactor pressure vessel is installed on the upper part of a reactor pressure vessel support pedestal, 1. A support structure for a reactor pressure vessel, characterized in that reinforcing ribs are provided radially below a bracket part that receives a load of the reactor pressure vessel, and the reinforcing ribs constitute a bracket receiving part that reinforces the bracket part. 2. The bracket part is integrally provided on the upper inner peripheral side of the reactor pressure vessel support pedestal, and the reinforcing ribs for reinforcing the bracket are vertical ribs arranged at intervals in the radial direction. A support structure for a nuclear reactor pressure vessel according to item 1. 3. The support structure for a nuclear reactor pressure vessel according to claim 1, wherein a space is formed between the reinforcing ribs and adjacent reinforcing ribs, and this space is set as an equipment arrangement space. 4. The support structure for a nuclear reactor pressure vessel according to claim 1, wherein the reinforcing rib is formed in a size and shape that supports the entire width of the bracket part, and the height of the bracket part is reduced. 5. Among the spaces formed between the reinforcing ribs, shell plates are installed between the reinforcing ribs in spaces that are not used for equipment placement, and concrete is placed in the area surrounded by the shell plates, reinforcing ribs, and the reactor pressure vessel support pedestal. A support structure for a nuclear reactor pressure vessel as set forth in claim 1, which is filled with the reactor pressure vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62016157A JPS63186185A (en) | 1987-01-28 | 1987-01-28 | Support structure of nuclear-reactor pressure vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62016157A JPS63186185A (en) | 1987-01-28 | 1987-01-28 | Support structure of nuclear-reactor pressure vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63186185A true JPS63186185A (en) | 1988-08-01 |
| JPH0556838B2 JPH0556838B2 (en) | 1993-08-20 |
Family
ID=11908668
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62016157A Granted JPS63186185A (en) | 1987-01-28 | 1987-01-28 | Support structure of nuclear-reactor pressure vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63186185A (en) |
-
1987
- 1987-01-28 JP JP62016157A patent/JPS63186185A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0556838B2 (en) | 1993-08-20 |
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