JPH0338720Y2 - - Google Patents
Info
- Publication number
- JPH0338720Y2 JPH0338720Y2 JP1984034867U JP3486784U JPH0338720Y2 JP H0338720 Y2 JPH0338720 Y2 JP H0338720Y2 JP 1984034867 U JP1984034867 U JP 1984034867U JP 3486784 U JP3486784 U JP 3486784U JP H0338720 Y2 JPH0338720 Y2 JP H0338720Y2
- Authority
- JP
- Japan
- Prior art keywords
- outer circumferential
- circumferential edge
- liner plate
- plate
- bearing plate
- 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
Links
- 239000004567 concrete Substances 0.000 claims description 10
- 238000003466 welding Methods 0.000 description 4
- 238000007689 inspection Methods 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 3
- 238000005452 bending Methods 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- 238000004873 anchoring Methods 0.000 description 1
- 238000005520 cutting process Methods 0.000 description 1
- 239000006249 magnetic particle Substances 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 239000011513 prestressed concrete 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
-
- 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)
- Buildings Adapted To Withstand Abnormal External Influences (AREA)
Description
【考案の詳細な説明】
〔考案の詳細な説明〕
従来のプレストレストコンクリート製原子炉格
納容器において、内部構造物、機器の碇着部を構
成する場合、第1図及び第2図に示すように同部
のライナプレートaを切欠いて厚板bを嵌合溶着
し、同厚板bにおける躯体コンクリートc側にベ
アリングプレートdとスタツドeとを別々に溶接
し、厚板(b)の格納容器内側には中間パツドfを溶
着していた。[Detailed description of the invention] [Detailed description of the invention] When configuring the internal structure and anchoring part of equipment in a conventional prestressed concrete reactor containment vessel, as shown in Figures 1 and 2, The liner plate a in the same area is notched, a thick plate b is fitted and welded, and a bearing plate d and a stud e are separately welded to the concrete frame c side of the same thick plate b, and the inside of the containment vessel of the thick plate (b) is welded. An intermediate pad f was welded to.
前記従来の構造においてはライナプレートaを
切欠いて厚板bを嵌合溶着するため、溶接量が多
い上にライナプレートaの変形量が多く、またベ
アリングプレートとスタツドとが近接しているた
め製作及び、溶接後の浸透探傷試験法、磁粉探傷
試験方法による検査に長時間を要する。 In the conventional structure, the liner plate a is notched and the thick plate b is fitted and welded, which requires a large amount of welding and deformation of the liner plate a.Also, the bearing plate and studs are close to each other, making it difficult to manufacture. In addition, it takes a long time to conduct inspections using penetrant testing methods and magnetic particle testing methods after welding.
本考案はこのような問題点を解決するために提
案されたもので、内面を気密用ライナプレートで
被覆したコンクリート製原子炉格納容器におい
て、スタツド付きベアリングプレートと中間パツ
ドとでライナプレートを挾着してなることを特徴
とするコンクリート製原子炉容器における荷重支
持構造に係るものである。 The present invention was proposed to solve these problems.In a concrete reactor containment vessel whose inner surface is covered with an airtight liner plate, the liner plate is clamped between a studded bearing plate and an intermediate pad. The present invention relates to a load supporting structure in a concrete reactor vessel characterized by comprising:
本考案においては前記したように、ライナプレ
ートを切欠くことなく、その両面よりスタツド付
きベアリングプレート及び中間パツドを挾着した
ので、ライナプレートによるコンクリート製格納
容器の気密性が低減されることなく、前記従来の
構造におけるようにライナプレートとその切欠部
に嵌着された厚板との溶接によるライナプレート
の溶接変形が防止される。 In the present invention, as described above, the studded bearing plate and the intermediate pad are clamped from both sides of the liner plate without cutting it, so the airtightness of the concrete containment vessel due to the liner plate is not reduced. This prevents welding deformation of the liner plate due to welding between the liner plate and the thick plate fitted into the notch as in the conventional structure.
また前記したように、ライナプレートはコンク
リート躯体側と原子炉格納容器内側との両面よ
り、スタツト付きベアリングプレートと中間パツ
ドとによつて挾着されているため、原子炉格納容
器内部の構造物、機器、配管等による荷重は気密
保持機能を負担するライナプレートに大きな応力
を生起させることなく、中間パツドからベアリン
グプレート及びスタツドに効率よく伝達でき、更
にスタツドはベアリングプレートに取付けられて
いるので、製作、検査が容易に行なわれる等、本
考案は多くの利点を有するものである。 Furthermore, as mentioned above, since the liner plate is held in place by the bearing plate with studs and the intermediate pad from both the concrete frame side and the inside of the reactor containment vessel, the structure inside the reactor containment vessel is Loads from equipment, piping, etc. can be efficiently transmitted from the intermediate pad to the bearing plate and studs without causing large stress on the liner plate, which is responsible for maintaining airtightness.Furthermore, since the studs are attached to the bearing plate, manufacturing is easier. The present invention has many advantages, such as ease of inspection.
以下本考案を図示の実施例について説明する。 The present invention will be described below with reference to the illustrated embodiments.
1は原子炉格納容器のコンクリート躯体2を被
覆するライナプレートで、同ライナプレート2の
コンクリート躯体側にはベアリングプレート3を
溶接し、その上にスタツド4を溶接し、また前記
ライナプレート2の原子炉格納容器内側には中間
パツド5を溶接し、同中間パツド5と前記ベアリ
ングプレート3とによつてライナプレート1を挾
着して荷重支持部を構成している。 1 is a liner plate that covers the concrete frame 2 of the reactor containment vessel, a bearing plate 3 is welded to the concrete frame side of the liner plate 2, a stud 4 is welded thereon, and the atoms of the liner plate 2 are welded to each other. An intermediate pad 5 is welded to the inside of the reactor containment vessel, and the liner plate 1 is clamped between the intermediate pad 5 and the bearing plate 3 to form a load support section.
なお前記ベアリングプレート3は中間パツド5
の外周縁の形状に合致するようにし、両者間の応
力の伝達が効果的に行なわれるように構成されて
いる。 Note that the bearing plate 3 is an intermediate pad 5.
The structure is made to match the shape of the outer peripheral edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumferential edge of the outer circumference of the outer circumference of the first and second parts of the first and second embodiments of the present invention.
而して図示の荷重支持構造によつて碇着された
原子炉格納容器内構造物、機器、配管等からの荷
重によつて中間パツド5に引張力V、剪断力S、
曲げモーメントMの反力が生起するが、剪断力S
に対してはベアリングプレート3が支持し、引張
力V、曲げモーメントMに対してはスタツド4が
支持するので、中間パツド5からベアリングプレ
ート3とスタツド4とに反力S,V,Mを伝達し
なければならない。而して図示の実施例によれば
スタツド4付きベアリングプレート3と中間パツ
ド5とによつてライナプレート1が挾着されてい
るので、気密保持の機能を負担するライナプレー
ト1に大きな応力を生起させることなく、中間パ
ツド4→ベアリングプレート3→スタツド4の順
で反力S,V,Mが効率よく伝達されるものであ
る。 As a result, tensile force V, shear force S,
A reaction force of bending moment M occurs, but shear force S
The bearing plate 3 supports the bearing plate 3, and the stud 4 supports the tensile force V and the bending moment M, so the reaction forces S, V, and M are transmitted from the intermediate pad 5 to the bearing plate 3 and the stud 4. Must. According to the illustrated embodiment, since the liner plate 1 is clamped by the bearing plate 3 with the studs 4 and the intermediate pad 5, a large stress is generated on the liner plate 1 which has the function of maintaining airtightness. The reaction forces S, V, and M are efficiently transmitted in this order from the intermediate pad 4 to the bearing plate 3 to the stud 4 without causing any interference.
また図示の実施例によれば従来のようにライナ
プレート1に切欠を設けることがないので、同ラ
イナプレート1の気密保持性能を低減させること
なく、またスタツド4はベアリングプレート3に
取付けられるので製作、検査が容易になる。 In addition, according to the illustrated embodiment, there is no cutout in the liner plate 1 as in the conventional case, so the airtightness of the liner plate 1 is not reduced, and the studs 4 can be attached to the bearing plate 3, making it easy to manufacture. , inspection becomes easier.
第1図は従来の原子炉格納容器の荷重支持構造
の正面図、第2図は第1図の矢視−図、第3
図は本考案に係るコンクリート原子炉格納容器に
おける荷重支持構造の一実施例を示す背面図、第
4図は第3図の矢視−図である。
1…ライナプレート、2…コンクリート躯体、
3…ベアリングプレート、4…スタツド、5…中
間パツド。
Figure 1 is a front view of the load support structure of a conventional reactor containment vessel, Figure 2 is a view taken from the arrow in Figure 1, and Figure 3 is
The figure is a rear view showing one embodiment of the load support structure in the concrete reactor containment vessel according to the present invention, and FIG. 4 is a view taken along the arrow in FIG. 3. 1...liner plate, 2...concrete frame,
3...Bearing plate, 4...Stud, 5...Intermediate pad.
Claims (1)
リート製原子炉格納容器において、スタツド付き
ベアリングプレートと中間パツドとでライナプレ
ートを挾着してなることを特徴とするコンクリー
ト製原子炉格納容器における荷重支持構造。 A load support structure for a concrete reactor containment vessel, the inner surface of which is covered with an airtight liner plate, the liner plate being clamped between a studded bearing plate and an intermediate pad.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1984034867U JPS60146895U (en) | 1984-03-13 | 1984-03-13 | Load support structure in concrete reactor containment vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1984034867U JPS60146895U (en) | 1984-03-13 | 1984-03-13 | Load support structure in concrete reactor containment vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60146895U JPS60146895U (en) | 1985-09-30 |
| JPH0338720Y2 true JPH0338720Y2 (en) | 1991-08-15 |
Family
ID=30538636
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1984034867U Granted JPS60146895U (en) | 1984-03-13 | 1984-03-13 | Load support structure in concrete reactor containment vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60146895U (en) |
-
1984
- 1984-03-13 JP JP1984034867U patent/JPS60146895U/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60146895U (en) | 1985-09-30 |
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