JPH0220960B2 - - Google Patents
Info
- Publication number
- JPH0220960B2 JPH0220960B2 JP56026637A JP2663781A JPH0220960B2 JP H0220960 B2 JPH0220960 B2 JP H0220960B2 JP 56026637 A JP56026637 A JP 56026637A JP 2663781 A JP2663781 A JP 2663781A JP H0220960 B2 JPH0220960 B2 JP H0220960B2
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- piping
- reactor containment
- hole
- cable tray
- 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 17
- 239000010959 steel Substances 0.000 claims description 17
- 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 6
- 239000012779 reinforcing material Substances 0.000 claims description 3
- 230000001629 suppression Effects 0.000 description 5
- 238000007689 inspection Methods 0.000 description 3
- 238000009434 installation Methods 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000010276 construction Methods 0.000 description 1
- 230000008602 contraction Effects 0.000 description 1
- 238000005553 drilling Methods 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000002787 reinforcement Effects 0.000 description 1
- 230000003014 reinforcing 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
- Supports For Pipes And Cables (AREA)
Description
【発明の詳細な説明】
本発明は原子炉格納容器の改良に係り、特に配
管類や電線管あるいはケーブルトレイの設置構造
を改善して格納容器内の有効スペースを拡大させ
た原子炉格納容器に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to the improvement of a nuclear reactor containment vessel, and particularly relates to a reactor containment vessel in which the effective space within the containment vessel is expanded by improving the installation structure of piping, electric conduits, or cable trays. .
一般に原子力発電所の原子炉格納容器は、原子
炉圧力容器を収納するドライウエルと、プール水
を貯えるサプレツシヨンチエンバと、これらのド
ライウエルとサプレツシヨンチエンバの間を連通
するベント管とから構成されている。上記ドライ
ウエル内の圧力容器ペデスタルと原子炉しやへい
壁との間には、パイプホイツプストラクチヤが構
築され、これを利用して各種の機械設備や配管、
配線管、ケーブルトレイ等が配置されるが、これ
らの設備類や配管類は種類と数が非常に多く、そ
れらの重量を支えるパイプホイツプストラクチヤ
も大掛りなものとなるため、ドライウエル内部の
機器配置スペースや配管スペースは制約を受け
る。特に配管や電線管あるいはケーブルトレイは
量が多い上、それらの敷設に際しては施工誤差や
熱移動および耐震上の理由から相互間あるいは他
の機器類や構造物等に対して十分なクリアランス
を必要とし、また梁部材との交叉点ではこれを迂
回するように敷設されているため設置スペースが
非常に大きくなる。 Generally, the reactor containment vessel of a nuclear power plant consists of a drywell that houses the reactor pressure vessel, a suppression chamber that stores pool water, and a vent pipe that communicates between these drywells and the suppression chamber. It is composed of. A pipe whip structure is constructed between the pressure vessel pedestal in the dry well and the reactor shield wall, and is used to connect various mechanical equipment, piping, etc.
Wire conduits, cable trays, etc. are arranged, but these equipment and piping come in many types and numbers, and the pipe whip structure that supports their weight is also large-scale. Internal equipment placement space and piping space are subject to restrictions. In particular, there is a large amount of piping, conduit, or cable trays, and when they are laid, sufficient clearance is required between each other or from other equipment or structures due to construction errors, heat transfer, and earthquake resistance. Furthermore, since the beam is laid so as to bypass the intersection with the beam member, the installation space becomes very large.
ここで第11図から第13図を参照してパイプ
ホイツプストラクチヤの粱10と配管11との交
叉点における迂回例を説明する。第11図および
第12図において、H型鋼より成るパイプホイツ
プストラクチヤの梁10を形成する下部フランジ
10bにはL型鋼30、Uボルト31を介して配
管11が配設されている。そして、他の梁32と
交叉する場所においては配管11は迂回され、第
13図に示される様な他の梁32に突設されたサ
ポート33によつて支持される構成になつてい
る。 Here, an example of a detour at the intersection of the pipe whip structure 10 and the pipe 11 will be described with reference to FIGS. 11 to 13. 11 and 12, a pipe 11 is disposed via an L-shaped steel 30 and a U-bolt 31 to a lower flange 10b forming a beam 10 of a pipe whip structure made of H-shaped steel. The pipe 11 is detoured at a place where it intersects with another beam 32, and is supported by a support 33 projecting from another beam 32 as shown in FIG.
このため、従来の原子炉格納容器では自由空間
が少なく、特に供用期間中検査スペースや人員通
路スペースの確保が非常に困難になつている。ま
た、配管類やケーブルトレイ等を固定支持するサ
ポートの必要個数が増え、これらの取付位置も、
耐震計算上から最適とされる位置の選定に制約を
受けることが多くなる。 For this reason, conventional reactor containment vessels have little free space, making it extremely difficult to secure inspection space and passage space for personnel, especially during the period of service. In addition, the required number of supports to securely support piping, cable trays, etc. has increased, and the mounting positions of these supports have also changed.
The selection of the optimal location is often constrained by seismic calculations.
本発明は上述の事情に鑑みてなされたもので、
原子炉格納容器内に構築されたパイプホイツプス
トラクチヤの水平梁や縦梁等の鉄骨構造物の梁の
少なくとも三方が前記梁の本体に遮蔽されて形成
される。残存空間を利用して各種配管やケーブル
トレイあるいは配線管等を敷設すると共に、この
敷設された鉄骨構造物の梁の残存空間を遮断する
他の鉄骨構造物と各種配管、配線管あるいはケー
ブルトレイとの干渉部分(以下交叉点と呼ぶ)に
はこの他の鉄骨構造物に貫通孔を穿設して配管類
を貫通させることにより機器類の配置スペースに
自由度を持たせ、有効スペースを拡大して使用期
間中検査や人員通路に要するスペースを確保し得
るようにした原子炉格納容器を提供することを目
的とするものである。 The present invention was made in view of the above circumstances, and
At least three sides of a beam of a steel structure such as a horizontal beam or a vertical beam of a pipe whip structure constructed in a reactor containment vessel are shielded by the main body of the beam. Utilize the remaining space to lay various types of piping, cable trays, raceways, etc., and also connect other steel structures and various types of piping, raceways, or cable trays that block the remaining space of the beams of the installed steel structure. By drilling through holes in other steel structures and passing piping through the interfering parts (hereinafter referred to as intersection points), we can provide flexibility in the arrangement space for equipment and expand the effective space. The purpose of the present invention is to provide a reactor containment vessel that can secure the space required for inspection and personnel passage during its use.
以下、図面を参照して本発明による原子炉格納
容器の一実施例を説明する。 Hereinafter, one embodiment of the reactor containment vessel according to the present invention will be described with reference to the drawings.
原子力発電所の原子炉格納容器1は、第1図お
よび第2図に例示するように、原子炉圧力容器2
を収納するドライウエル3と、プール水4を貯え
るサプレツシヨンチエンバー5と、これらのドラ
イウエルとサプレツシヨンチエンバーの間を連通
するベン管6とから構成されている。 As illustrated in FIGS. 1 and 2, a reactor containment vessel 1 of a nuclear power plant includes a reactor pressure vessel 2.
A suppression chamber 5 stores pool water 4, and a vent pipe 6 communicates between the dry well and the suppression chamber.
ドライウエル3内には圧力容器ペデスタル7と
原子炉遮蔽壁8の周囲にパイプホイツプストラク
チヤ9が構築され、これを利用して各種の機械設
備や配管、電線管やケーブルトレイ等が設置され
る。 Inside the dry well 3, a pipe whip structure 9 is constructed around the pressure vessel pedestal 7 and the reactor shielding wall 8, and various mechanical equipment, piping, electrical conduits, cable trays, etc. are installed using this structure. be done.
第3図と第4図はパイプホイツプストラクチヤ
の粱10がH型鋼より成る場合、この粱の上下の
フランジ10a,10b、ウエブ10dで遮蔽さ
れて形成される残存空間10c内に小口径配管1
1を添設し、Uボルト12を用いてサポートした
例を示す。 FIGS. 3 and 4 show that when the pipe whip structure 10 is made of H-beam steel, a small-diameter Piping 1
1 is attached and supported using U bolts 12.
第5図と第6図は小口径配管11がH型鋼より
なる粱10と交叉する場合、この交叉点における
梁のウエブに配管貫通孔13を設け、この孔に配
管11を挿通させた例を示す。この場合、配管1
1は貫通孔13の前後で支持架台14上に載置さ
れ、Uボルト12によつて支持固定される。な
お、梁の貫通口部は必要に応じて補強材(図示せ
ず)により補強される。 Figures 5 and 6 show an example in which, when a small-diameter pipe 11 intersects with a pipe 10 made of H-shaped steel, a pipe through hole 13 is provided in the web of the beam at this intersection point, and the pipe 11 is inserted into this hole. show. In this case, pipe 1
1 is placed on a support pedestal 14 before and after the through hole 13, and is supported and fixed by U bolts 12. Note that the through-hole portion of the beam is reinforced with a reinforcing material (not shown) as necessary.
第7図と第8図はケーブルトレイ15がH型鋼
よりなる梁10と交叉する場合、この交叉点にお
ける梁に矩形状の貫通孔16を透設し、この孔に
ケーブルトレイ15を挿通させた例を示す。この
場合、ケーブルトレイ15は貫通孔16の前後で
支持粱台14上に載置され、ボルトナツト17を
用いて固定される。18は貫通孔部を補強する補
強材を示す。 FIGS. 7 and 8 show that when the cable tray 15 intersects with the beam 10 made of H-shaped steel, a rectangular through hole 16 is provided in the beam at the point of intersection, and the cable tray 15 is inserted through this hole. Give an example. In this case, the cable tray 15 is placed on the support pedestal 14 before and after the through hole 16, and is fixed using bolts and nuts 17. Reference numeral 18 indicates a reinforcing material for reinforcing the through hole portion.
第9図と第10図は小口径配管11が箱型鋼よ
り成る粱19と交叉する場合、この交叉点におけ
る梁に貫通孔20を設け、この孔に配管11を挿
通させた例を示す。この場合、貫通孔20には、
両端内方に4対ずつのガイド21を突設させたス
リーブ22を挿入固定し、配管11側にも前記ガ
イド22に摺動自在に係合する突起23を形成し
て配管11の熱伸縮等による軸方向への移動を許
容する。 9 and 10 show an example in which, when a small-diameter pipe 11 intersects with a pipe 19 made of box-shaped steel, a through hole 20 is provided in the beam at the crossing point, and the pipe 11 is inserted into this hole. In this case, the through hole 20 has
A sleeve 22 with four pairs of guides 21 protruding inward from both ends is inserted and fixed, and a protrusion 23 is formed on the piping 11 side to slidably engage with the guides 22 to prevent thermal expansion and contraction of the piping 11. Allows for axial movement due to
以上、本発明を4実施例につき説明したが、こ
れらの実施例から明らかなように本発明によれば
配管類を梁に添架することにより梁の少なくとも
三方が前記梁の本体に遮蔽されて形成される残存
空間を配管類の設置スペースとして有効に利用す
ることができ、また梁との交叉点では梁に貫通孔
を設けてこれに挿通させるようにしたから、これ
を迂回させる場合に必要とされた占有面積が不要
となる上、梁貫通部でサポートをとることができ
るため、サポートに必要なスペースを減少させる
ことができる。 The present invention has been described above with reference to four embodiments, but as is clear from these embodiments, according to the present invention, by attaching piping to a beam, at least three sides of the beam are shielded by the main body of the beam. The remaining space can be effectively used as installation space for piping, and since a through hole is provided in the beam at the intersection with the beam, it is possible to pass through the hole, which is necessary when bypassing the hole. In addition to eliminating the need for additional occupied area, support can be provided at the beam penetrating portion, so the space required for support can be reduced.
従つて、ドライウエル内における有効スペース
が拡大し、各種機器類や配管設置の自由度が増大
する上、供用期間中検査や人員通路スペースを余
裕をもつて確保することが可能となる。 Therefore, the effective space within the dry well is expanded, the degree of freedom in installing various equipment and piping is increased, and it is possible to secure sufficient passage space for inspection and personnel during the service period.
なお、本発明は第1図に示すMARKI型原子炉
格納容器に限らず、同型や同型の格納容器に
も同様に適用し得ることは勿論である。 It goes without saying that the present invention is not limited to the MARKI type nuclear reactor containment vessel shown in FIG. 1, but can be similarly applied to containment vessels of the same type or the same type.
第1図は本発明による原子炉格納容器の一例を
示す概念的な縦断面図、第2図は第1図のA−A
線に沿う概念的横断端面図、第3図は本発明にお
いて配管をH型鋼製の梁に沿つて設置した例を示
す側面図、第4図はその横断面図、第5図は本発
明において配管をH型鋼製の梁に貫通支持させた
例を示す側面図、第6図はその横断面図、第7図
は本発明においてケーブルトレイをH型鋼製の梁
に貫通支持させた例を示す側面図、第8図はその
横断面図、第9図は本発明において配管を箱型鋼
製の梁に貫通支持させた例を示す側面図、第10
図はその横断面図、第11図は配管をH型鋼製の
パイプホイツプストラクチヤの梁に沿つて設置し
た従来例を示す側面図、第12図は第11図のB
−B矢視断面図、第13図は第11図のC−C矢
視断面図である。
1…原子炉格納容器、2…原子炉圧力容器、3
…ドライウエル、4…プール水、5…サプレツシ
ヨンチエンバー、6…ベント管、7…圧力容器ペ
デスタル、8…原子炉遮蔽壁、9…パイプホイツ
プストラクチヤー、10…梁、11…配管、12
…Uボルト、13…貫通孔、14…支持架台、1
5…ケーブルトレイ、16…貫通孔、18…補強
材、19…梁、20…貫通孔、21…ガイド、2
2…スリーブ、23…突起。
FIG. 1 is a conceptual vertical cross-sectional view showing an example of a nuclear reactor containment vessel according to the present invention, and FIG. 2 is an A-A in FIG.
A conceptual cross-sectional end view taken along the line, Fig. 3 is a side view showing an example in which piping is installed along an H-shaped steel beam in the present invention, Fig. 4 is a cross-sectional view thereof, and Fig. 5 is a cross-sectional view of the present invention. Fig. 6 is a cross-sectional view of the pipe, and Fig. 7 is a side view showing an example in which the piping is supported through the H-shaped steel beam in the present invention. FIG. 8 is a side view showing an example, FIG. 8 is a cross-sectional view thereof, FIG.
The figure is a cross-sectional view, Figure 11 is a side view showing a conventional example in which piping is installed along the beam of a pipe whip structure made of H-shaped steel, and Figure 12 is B of Figure 11.
13 is a cross-sectional view taken along the line CC in FIG. 11. 1...Reactor containment vessel, 2...Reactor pressure vessel, 3
... Dry well, 4... Pool water, 5... Suppression chamber, 6... Vent pipe, 7... Pressure vessel pedestal, 8... Reactor shielding wall, 9... Pipe whip structure, 10... Beam, 11... Piping, 12
... U bolt, 13 ... Through hole, 14 ... Support frame, 1
5... Cable tray, 16... Through hole, 18... Reinforcement material, 19... Beam, 20... Through hole, 21... Guide, 2
2...Sleeve, 23...Protrusion.
Claims (1)
の少なくとも三方が前記梁の本体に遮蔽されて形
成される残存空間に各種配管、電線管あるいはケ
ーブルトレイを敷設し、この敷設された鉄骨構造
物の梁の前記残存空間を遮断する鉄骨構造物と各
種配管、電線管あるいはケーブルトレイとの干渉
部分には残存空間を遮断する鉄骨構造物に前記各
種配管、電線管あるいはケーブルトレイが貫通す
る貫通孔が穿設されて成ることを特徴とする原子
炉格納容器。 2 前記配管、電線管あるいはケーブルトレイ、
残存空間においてサポートを介して支持されて成
ることを特徴とする特許請求の範囲第1項記載の
原子炉格納容器。 3 前記サポートは、前記配管、電線管あるいは
ケーブルトレイを載置しかつ貫通孔の前後に配設
された支持架台から成ることを特徴とする特許請
求の範囲第2項記載の原子炉格納容器。 4 前記サポートは、貫通孔内壁面に配設された
補強材であることを特徴とする特許請求の範囲第
2項記載の原子炉格納容器。 5 前記サポートは、前記配管、電線管あるいは
ケーブルトレイを軸方向に移動自在に支持し、か
つ前記貫通孔に挿通されたスリーブから成ること
を特徴とする特許請求の範囲第2項記載の原子炉
格納容器。 6 前記スリーブとこれに挿通させた前記配管、
電線管あるいはケーブルトレイの間にガイドとこ
れに摺動自在に係合する突起を設けたことを特徴
とする特許請求の範囲第5項記載の原子炉格納容
器。[Scope of Claims] 1. Laying various piping, electrical conduit or cable trays in the remaining space formed by at least three sides of the beam of the steel structure built in the reactor containment vessel being shielded by the main body of the beam, At the interference part between the steel structure that blocks the remaining space of the beam of the laid steel structure and various piping, conduit, or cable tray, the steel structure that blocks the remaining space may A nuclear reactor containment vessel characterized by being formed with a through hole through which a cable tray passes. 2 the piping, conduit or cable tray;
The reactor containment vessel according to claim 1, wherein the reactor containment vessel is supported via a support in the remaining space. 3. The reactor containment vessel according to claim 2, wherein the support comprises a support pedestal on which the piping, electric conduit, or cable tray is placed and which is disposed before and after the through hole. 4. The reactor containment vessel according to claim 2, wherein the support is a reinforcing material disposed on the inner wall surface of the through hole. 5. The nuclear reactor according to claim 2, wherein the support supports the piping, conduit, or cable tray in an axially movable manner and is comprised of a sleeve inserted into the through hole. Containment vessel. 6 the sleeve and the pipe inserted through the sleeve;
A nuclear reactor containment vessel according to claim 5, characterized in that a guide and a protrusion slidably engaged with the guide are provided between the electric conduit or the cable tray.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP56026637A JPS57141597A (en) | 1981-02-25 | 1981-02-25 | Nuclear reactor container |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP56026637A JPS57141597A (en) | 1981-02-25 | 1981-02-25 | Nuclear reactor container |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS57141597A JPS57141597A (en) | 1982-09-01 |
JPH0220960B2 true JPH0220960B2 (en) | 1990-05-11 |
Family
ID=12198957
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP56026637A Granted JPS57141597A (en) | 1981-02-25 | 1981-02-25 | Nuclear reactor container |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS57141597A (en) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS57147092A (en) * | 1981-03-09 | 1982-09-10 | Tokyo Shibaura Electric Co | Pipe whip structure of nuclear reactor |
JPS5815007U (en) * | 1981-07-20 | 1983-01-29 | ナショナル住宅産業株式会社 | Offcut processing equipment |
JPS60122896U (en) * | 1984-01-27 | 1985-08-19 | 石川島播磨重工業株式会社 | Support structure of pipe whip structure for reactor containment vessel |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5298096U (en) * | 1976-01-22 | 1977-07-23 |
-
1981
- 1981-02-25 JP JP56026637A patent/JPS57141597A/en active Granted
Also Published As
Publication number | Publication date |
---|---|
JPS57141597A (en) | 1982-09-01 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
KR102237330B1 (en) | Steam Generator Tube Support | |
CN101430939B (en) | Electric penetration piece with radiation shielding structure | |
JPS5945115B2 (en) | Support device for nuclear boiler with pressure vessel and steam generator | |
JPH0220960B2 (en) | ||
JP3739868B2 (en) | Nuclear power plant | |
US4786462A (en) | Support structure for a nuclear reactor | |
EP0162956A2 (en) | Modular liquid metal nuclear reactor | |
KR102523740B1 (en) | Metal structures for supporting fluid ducts and industrial facilities including these metal structures | |
JP6882938B2 (en) | Foundation members and seismic retrofitting methods | |
JPH0138280B2 (en) | ||
JP2709140B2 (en) | Power plant and steam turbine support | |
JP2613637B2 (en) | Nuclear power plant | |
JP2945706B2 (en) | Reactor pressure vessel support base | |
JPS5918494A (en) | Method of fixing pipe on pipe through portion of reactor container | |
JPS5825360Y2 (en) | Support device for lead-shielded piping | |
JPS5936236B2 (en) | steel containment vessel | |
JPH0416602B2 (en) | ||
JPS6024437B2 (en) | Pedestal structure of reactor pressure vessel | |
JPH08262174A (en) | Structure of reactor building | |
JP2003207588A (en) | Construction method of nuclear reactor building | |
Braudway | A new state of the art standards facility | |
JPH0315159B2 (en) | ||
JPS63284493A (en) | Frame for supporting reactor pressure vessel | |
JPS61105386A (en) | Piping pipe-group support structure | |
JPS61286462A (en) | Integral suspension construction method of iron beam and pipings of atomic power plant building |