JPS60102591A - Structure in nuclear reactor - Google Patents
Structure in nuclear reactorInfo
- Publication number
- JPS60102591A JPS60102591A JP58208932A JP20893283A JPS60102591A JP S60102591 A JPS60102591 A JP S60102591A JP 58208932 A JP58208932 A JP 58208932A JP 20893283 A JP20893283 A JP 20893283A JP S60102591 A JPS60102591 A JP S60102591A
- Authority
- JP
- Japan
- Prior art keywords
- head
- reactor
- reactor pressure
- stand pipe
- standpipe
- 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.)
- Pending
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
- Particle Accelerators (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】
〔発明の技術分野〕
本発明は、沸騰水型原子炉の炉内構造物に関する０
〔発明の技術的背景〕
一般にθド騰水型原子炉は第１図に示′ｊ様な構造にな
っている。同図において、原子炉圧力容器１内にはシュ
ラウド２が収容されている。このシュラウド２の上端に
は上部格子板３が、下部には炉心支持板４が設置されて
いる。またこの／ニラウド２内には炉心を構成する燃料
束合体５が多数状８されており、この燃料糸は本５の上
部は上部格子板３．ｉ’部は炉心支ｊｖ−板４によって
支持されている。／ニラウド３の上１＠ｖｃは、椀状の
ンｄラウドヘッド６が７ユラウドヘソドボルト７によっ
て締結されている。この７ユラウドヘツド６には、多数
のスタッドバイブ８が植設さＪしており、このスタッド
パイプ８間には補強板９が設けられてぃる。このスタッ
ドバイブ；の上４Ｖｃは、それぞれ気水分離Ｘ７１０が
配設されている。この気水分離層１０の上刃Ｖこは蒸気
乾燥ａｌｔが配置されている。沸ｊ違水型原子炉ＶＣお
ける圧力谷器同の冷却材の流れは炉心を構成′Ｊ−ゐ燃
料集合体５内で沸纏し、水と蒸気の二相υ１しとなって
７ユラウドヘソド６に流れる。／ニラウドヘット６内の
水と蒸気はさらＶこスタッドバイブ８を通り、気水分離
詣１ｔＪで水と蒸気とＶＣ分ｔ？ｌ＆され、分＋ｑｌｉ
された蒸気は蒸気！ｉ燥６鋒１１で乾燥さｉＬだのち主
蒸気ノズル１２から主蒸スヘ管を介して図示しないター
ビンに送られるよってなっている。ｊた原子炉圧力容器
ｌには原子炉圧力容器ｌ内壁に設けられた給水スパーン
ャ１３へｊ京子炉圧力容詣ｌ外から冷却水を尋く給水人
口ノズル１４が杉１戊されている。池ｖ’ｃ原子炉圧力
「子゛詣ｌ内−・？ｉ却水を棉〈ノズルとして原子炉圧
力容Ｒ３ｌには炉心スプレノズル１５が形成されている
。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to internal structures of boiling water reactors. ′j-like structure. In the figure, a shroud 2 is housed within a reactor pressure vessel 1. An upper grid plate 3 is installed at the upper end of this shroud 2, and a core support plate 4 is installed at the lower part. In addition, a large number of combined fuel bundles 5 composing the reactor core are arranged in this /Niroud 2, and the upper part of the fuel bundles 5 is connected to the upper lattice plate 3. The i' portion is supported by the core support JV-plate 4. A bowl-shaped cloud head 6 is fastened to the top 1@vc of the /nilaud 3 by a seven-pound hesod bolt 7. A large number of stud vibes 8 are embedded in this seven-round head 6, and reinforcing plates 9 are provided between the stud pipes 8. A steam/water separator X710 is installed on the upper 4Vc of this stud vibe. A steam drying alt is disposed on the upper blade V of this steam/water separation layer 10. The flow of the coolant in the pressure trough in the reactor VC boils in the fuel assembly 5 that constitutes the reactor core, becoming two-phase water and steam υ1. flows to / The water and steam in the Niraud head 6 further passes through the V stud vibe 8, and the water, steam, and VC are separated by a steam separation circuit. l & been, min + qli
Steam is steam! After being dried in a dryer 11, it is sent from a main steam nozzle 12 to a turbine (not shown) via a main steam pipe. A water supply nozzle 14 for supplying cooling water from outside the reactor pressure vessel 1 to a water supply spanner 13 provided on the inner wall of the reactor pressure vessel 1 is installed in a cedar wood. A core spray nozzle 15 is formed in the reactor pressure volume R3l as a nozzle to spray coolant water inside the reactor pressure volume R3l.
多数のスタッドバイブ８は、シュラウドヘッド６の中心
部ＶＣ植設されているもののみが１１０強板９に連結さ
れており、シュラウドヘッド６の外周部に位置するスタ
ッドパイプ８は７ユフウドヘノド６との植設部によって
のみ支持される溝道となっている。そのため、このシュ
ラウドヘッド６の外周部ＶＣ位置するスタンドパイプ８
の剛性は、他に位置スるスタッドバイブ８の剛性と比Ｉ
ｌ夕して非常Ｖこ小すく、シュラウドヘッド６やスタッ
ドバイブ８の共振により７ユラウドヘソド６外周部のス
タッドパイプ８がＶ杉するおそ才しがあった。Of the many stud vibes 8, only the one with the VC implanted in the center of the shroud head 6 is connected to the 110 strong plate 9, and the stud pipes 8 located on the outer periphery of the shroud head 6 are connected to the 7-Yufuudhenod 6. The ditch is supported only by the planted parts. Therefore, the stand pipe 8 located at the outer peripheral part VC of this shroud head 6
The rigidity of is the ratio of the rigidity of the stud vibe 8 placed elsewhere.
In the evening, the V was very small, and due to the resonance of the shroud head 6 and stud vibe 8, there was a possibility that the stud pipe 8 on the outer circumference of the shroud head 6 would become V-shaped.
本発明の目的Ｑよスタンドパイプの剛性を同上させ、シ
ュラウドヘッドやスタッドバイブの共振によるスタンド
パイプの変形がない原子炉内構造′１勿を提供すること
ＶＣ６る。An object of the present invention is to provide a nuclear reactor internal structure in which the rigidity of the stand pipe is increased and the stand pipe is not deformed due to resonance of the shroud head or stud vibrator.
〔元りｊの５直要〕
本発明は、原子炉圧力容器内の上部格子板上方に設けら
れたシュラウドヘッドと、このシュラウドヘッドに植設
されたスタッドバイブと、このスタンドパイプに連結し
さらにト部全７ユラウドヘツドに同者された補強板とか
ら成ることを特徴とする原子炉炉内構造物である。[5 shifts of original J] The present invention provides a shroud head provided above an upper lattice plate in a reactor pressure vessel, a stud vibe implanted in this shroud head, and a stud vibe connected to this stand pipe. This is a nuclear reactor internal structure characterized by comprising a reinforcing plate attached to a total of seven roof heads.
以ト一本発明の一実施例を第２図および第３図を参照し
て説明する。なお、第２図は本発明に係る原子炉内構造
物の要部のみ示し原子炉圧力Ｗｌ＜内の上部および炉心
以Ｆを省略した縦田１面図である。An embodiment of the present invention will now be described with reference to FIGS. 2 and 3. Note that FIG. 2 is a vertical view showing only the essential parts of the reactor internal structure according to the present invention, omitting the upper part within the reactor pressure Wl< and the part F below the reactor core.
同図において従来例と同一部分１ｃは同一符号を付し説
明は省略する。本実施例において原子炉圧力容器１内に
収容されているシュラウド２の上部に設けられたシュラ
ウドヘッド６には多数のスタンドパイプ８が植設されて
いる。このスタンドパイプ８の止痛には気水分離凝１０
が配設されている。In the figure, portions 1c that are the same as those in the conventional example are given the same reference numerals and explanations will be omitted. In this embodiment, a large number of standpipes 8 are installed in a shroud head 6 provided at the upper part of a shroud 2 housed in a reactor pressure vessel 1. To stop the pain of this standpipe 8, air-water separation and coagulation 10
is installed.
ここで第３図ＶＣ第２図のＡ−Ａ矢伐図を示′ｊ。同図
で示される様に前記スタッドバイブ８は、シュラウドヘ
ッド６の中心に位置するスタッドバイブ８からたとえば
六方向へ放射状に配設されて−いる補強板１６によって
支持されている。この補強板１６はト都をシュラウドヘ
ッド６に固層させている。Here, the A-A cross-sectional view of FIG. 3 VC and FIG. 2 is shown. As shown in the figure, the stud vibrator 8 is supported by reinforcing plates 16 which are arranged radially in, for example, six directions from the stud vibrator 8 located at the center of the shroud head 6. This reinforcing plate 16 fixes the cap to the shroud head 6.
以上のように青酸された原子炉内構造物は、スタッドバ
イブ８が補強板１６によって４：結され、シュラウドヘ
ッド６ｖＣ固２’ｔＪｔされているのでスタンドバイグ
８部分の剛性を大幅に向上させることができる。In the reactor internal structure coated with cyanide as described above, the stud vibrator 8 is tied by the reinforcing plate 16, and the shroud head is fixed by 6vC, so the rigidity of the stand vibrator 8 portion is greatly improved. be able to.
つきＶＣ−第４しｊからｙＦ ８図を基にして他の実施
例を説明づ−る。絹・１図は本発明の他の実施例を示す
原子炉圧力容器の部分縦…１面である。同図において第
２図と同一部分には同一符号を付し説明は省略する。本
実施例においてスタンドパイプ８を支持し、シュラウド
ヘッド６に溶接時で固層されている補強板１７はスタッ
ドバイブ８の最外周よりさらに原子炉圧力容器１’ｔで
のびて支持用アーム１８を形成している。ここで第５図
に第４図のＨ−Ｂ矢視図を示す。同図に示す様に支持用
アーム１８はシュラウドヘッド６の中心より六方向へ放
射状に配設され原子炉圧力容器ＩＫ固定されている。前
記シュラウドヘッド６の外周近傍ＶＣはシュラウドヘッ
ド６の外周に沿って円環状のリング２１が設けられてい
る。Other embodiments will be explained based on Figure 8. Figure 1 is a partial longitudinal view of a nuclear reactor pressure vessel showing another embodiment of the present invention. In this figure, the same parts as in FIG. 2 are given the same reference numerals, and their explanation will be omitted. In this embodiment, the reinforcing plate 17 that supports the stand pipe 8 and is fixed to the shroud head 6 during welding extends further from the outermost periphery of the stud vibe 8 in the reactor pressure vessel 1't and supports the supporting arm 18. is forming. Here, FIG. 5 shows a view taken along the line HB in FIG. 4. As shown in the figure, the support arms 18 are arranged radially in six directions from the center of the shroud head 6 and are fixed to the reactor pressure vessel IK. Near the outer periphery VC of the shroud head 6, an annular ring 21 is provided along the outer periphery of the shroud head 6.
ここで支持用アームの実施例を第６図よシ第８図に示す
。第６図および第７図は第４図の支持用アーム部分？ホ
す平向図及び側面図である。この第６図および第７図に
おいて、この方向に位置するスタンドパイプ８の間には
補強板１７がぞｄ接等で固着さノしている。／ニラウド
ヘッド６の最外周Ｖこ位置するスタンドバイ１Ｂ ＶＣ
は、補強板１７と同一方向に配設さｔ’Ｌる支持用アー
ム１８の一端が４接等で固着されている。支持用アーム
１８の細組ｊＩ面が１゛字ＩＩ≧状をした突起１９を形
成している。この父起１９は、原子炉圧力谷ｇｉｌの内
周面に溶接者で固着された曲面がＣ字形状をしたブラケ
ット２ｏＰ３ｖｃ挿入文付されている。前記支持用アー
ム１８Ｖｃは、シュラウドヘソド６の外周、ＩＨｙｃ沿
って設けられた円環状のり／グ２工がｍ接固定されてい
る。以上のイイｑ成より本来ＪＭ例においては弔−の実
施例よりさらに剛性を尚めることができる。Examples of the support arm are shown in FIGS. 6 and 8. Are Figures 6 and 7 the support arm part of Figure 4? FIG. 2 is a plan view and a side view. In FIGS. 6 and 7, a reinforcing plate 17 is fixed between the stand pipes 8 located in this direction by a d-joint or the like. /Standby 1B VC located at the outermost circumference of the Niloud head 6
In this case, one end of a supporting arm 18, which is disposed in the same direction as the reinforcing plate 17, is fixed to the reinforcing plate 17 with a four-way joint or the like. The narrow JI surface of the support arm 18 forms a protrusion 19 shaped like the letter II≧. This protrusion 19 has a bracket 2oP3vc insert with a C-shaped curved surface fixed by a welder to the inner peripheral surface of the reactor pressure valley gil. An annular glue/glue 2 provided along the outer periphery of the shroud head 6 and IHyc is fixed to the supporting arm 18Vc in m-contact. Due to the above-mentioned good q configuration, the rigidity of the JM example can be improved more than that of the original example.
なお、第８図に示すように、補強板２２および支持用ア
ーム２３に穴２２ａ、２３ａを穿設する場合には、シュ
ラウドヘッド６上Ｖｃ戒置ざバる補強板２２および支持
用アーム２３の道、−が軽減され、より健全性の高い原
子炉内構造物を提供することができる。As shown in FIG. 8, when holes 22a and 23a are formed in the reinforcing plate 22 and the supporting arm 23, the holes 22a and 23a are formed in the reinforcing plate 22 and the supporting arm 23 where Vc is not placed on the shroud head 6. Therefore, it is possible to provide a more sound reactor internal structure.
本発明によれはスタンドパイプの剛性を大幅に向上させ
、／ニラウドヘッドやスタンドパイプの共Ｊａによるス
タンドパイプの′Ｒ杉のない原子炉炉内）倚造°吻を提
供することができる。According to the present invention, the rigidity of the standpipe can be greatly improved, and it is possible to provide a structure for the standpipe (within a nuclear reactor) that does not have a cedar structure due to the joint structure of the standpipe and the head of the standpipe.
第１図は従来の原子炉圧力容器のｗｃｍ＋面図、第２図
は本発明に係る原子炉内構造物の一実施例を示す縦曲面
図、第３図はＡ２図のＡ−Ａ矢尻図、第４図は本発明に
係る原子炉内構造物の他の実施例を示′ｊ−縦１１１１
面図、第５図は第４図の１３−Ｂ矢伐図、第６図は第２
図における補強板と支持アームの取付状！Ｉ！４全示す
平面図、第７図は第６図の側面図、第８図は第４図てお
ける補強板と支持アームの側面図である。
６・・シュラウドヘノド ８・・スタントノ（イブ１６
・・補強板 １７・・補強板
１８・・支持用アーム ２０・・プラケット２１・・リ
ング ２２・・・曲強板
２３・・支持用アーム
代理人 升理士 則 近 憲 佑 （ほか１名）第１図
第２図
第３図 第５図
第４図
第６図
第７図
第８図Fig. 1 is a wcm + side view of a conventional reactor pressure vessel, Fig. 2 is a vertical curved view showing an embodiment of the reactor internal structure according to the present invention, and Fig. 3 is an A-A arrowhead view of Fig. A2. , FIG. 4 shows another embodiment of the reactor internal structure according to the present invention'j-vertical 1111
The top view, Figure 5 is the 13-B cross-sectional view of Figure 4, and Figure 6 is the 2nd
The installation of the reinforcing plate and support arm in the figure! I! 4. FIG. 7 is a side view of FIG. 6, and FIG. 8 is a side view of the reinforcing plate and support arm in FIG. 4. 6. Shroud Henod 8. Stantono (Eve 16
・・Reinforcement plate 17・・・Reinforcement plate 18・・・Supporting arm 20・・・Plucket 21・・・Ring 22・・・Curved strong board 23・・・Supporting arm representative Masu Rishi Nori Chika Kensuke (and 1 other person) No. Figure 1 Figure 2 Figure 3 Figure 5 Figure 4 Figure 6 Figure 7 Figure 8
Claims (4)
たシュ２ウドヘツドと、このシュラウドヘッドＶＣ４１
１１設ざＩしたスタンドパイプと、このスタンドパイプ
に連結しさらに１・部を７ユラウドヘソドに固盾さノ１
．ノヒ浦強板とから成ることを特徴とする原子炉炉内ｉ
’、！ ｉｎ物。(1) Shroud head provided above the upper grid plate in the reactor pressure valley and this shroud head VC41
11 The standpipe that was set up, and the 1 part connected to this standpipe, and the solid shield part 1 to 7 euros.
．． A nuclear reactor interior i characterized by consisting of a Nohiura hard plate
',! In thing.
シュラウドヘッドと、この７ユラウト′−＼ラドＶこ植
設されたスタンドパイプと、このスタンドパイプに連結
しさらにト部を７ユラウドヘノドに固層された補強板と
、前記スタンドパイプＶこ一端を連結させ他端を原子炉
圧力′、８’ｒ：ｉ内面に固定される支づ、ｒ用アーム
とから成ることを特徴とする原子炉炉内構造・吻。(2) The shroud head installed above the upper lattice plate in the reactor pressure vessel, the standpipe planted in this 7-layer head, and the 7-layer head connected to this stand pipe, and the It is characterized by comprising a reinforcing plate fixed to the stand pipe V, and a support arm for connecting one end of the stand pipe V and having the other end fixed to the inner surface of the reactor pressure. Reactor internal structure/proboscis.
ｐｃ ＋ａつて設けられた円環状のす／グＶこそれぞれ
連結し゛ていることを特徴とする特許請求の範囲第２項
記載の原子炉炉内構造物っ(3) The nuclear reactor according to claim 2, wherein the support arm is connected to annular rings provided near the outer slender part of the /Ni-loud head. Internal structure
され他端を原子炉圧力谷詣内面に杉ｉ戊されたプラケッ
トに挿入されていることを特徴とする特許請求の相聞菖
２項第３項記載の原子炉炉内構造物。(4) The support arm has one end connected to the stand pipe and the other end inserted into a placket drilled into the inner surface of the reactor pressure valley, Paragraph 2, Paragraph 3 of the patent claim. Nuclear reactor internals described in Section 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58208932A JPS60102591A (en) | 1983-11-09 | 1983-11-09 | Structure in nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58208932A JPS60102591A (en) | 1983-11-09 | 1983-11-09 | Structure in nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS60102591A true JPS60102591A (en) | 1985-06-06 |
Family
ID=16564513
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58208932A Pending JPS60102591A (en) | 1983-11-09 | 1983-11-09 | Structure in nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60102591A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1995029487A1 (en) * | 1994-04-22 | 1995-11-02 | General Electric Company | Reactor core shroud repair with welded brackets |
| US5530219A (en) * | 1994-04-22 | 1996-06-25 | General Electric Company | Reactor core shroud repair with welded brackets |
| WO1997004461A1 (en) * | 1995-07-21 | 1997-02-06 | Combustion Engineering, Inc. | Method and apparatus for repair of nuclear reactor shroud |
| US5670072A (en) * | 1994-04-22 | 1997-09-23 | General Electric Company | Method and apparatus for joining metal components with mitigation of residual stresses |
-
1983
- 1983-11-09 JP JP58208932A patent/JPS60102591A/en active Pending
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1995029487A1 (en) * | 1994-04-22 | 1995-11-02 | General Electric Company | Reactor core shroud repair with welded brackets |
| US5530219A (en) * | 1994-04-22 | 1996-06-25 | General Electric Company | Reactor core shroud repair with welded brackets |
| US5670072A (en) * | 1994-04-22 | 1997-09-23 | General Electric Company | Method and apparatus for joining metal components with mitigation of residual stresses |
| WO1997004461A1 (en) * | 1995-07-21 | 1997-02-06 | Combustion Engineering, Inc. | Method and apparatus for repair of nuclear reactor shroud |
| US5623526A (en) * | 1995-07-21 | 1997-04-22 | Combustion Engineering, Inc. | Method and apparatus for repair of nuclear reactor shroud |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JPS61168701A (en) | Module type steam separator | |
| US4573526A (en) | Steam generator flow control device | |
| JPS60102591A (en) | Structure in nuclear reactor | |
| TWI780059B (en) | Floating support structure comprising a floater and a heave plate provided with a row of orifices | |
| CN208501625U (en) | A kind of High-Rise Pile Cap Foundation berthing member connection structure | |
| JPH04232495A (en) | Pressure container of atomic reactor | |
| US6059022A (en) | Steam generation with tube support | |
| JPS606895A (en) | Containment vessel | |
| JP2772109B2 (en) | Floating offshore structure | |
| RU2242811C2 (en) | Device for screwing neutron reflector and method for its screwing | |
| JPS61122495A (en) | Vibrationproof bar and arranging and mounting method thereof | |
| JPH0862372A (en) | Internal structure of pressurized water reactor | |
| JPS5868695A (en) | Device for supporting instrument in reactor | |
| JPS60117184A (en) | Shroud head | |
| CN108560496A (en) | A kind of High-Rise Pile Cap Foundation berthing member connection structure and construction method | |
| JPH11269850A (en) | Jellyfish prevention net for intake tower | |
| JP2618789B2 (en) | Lower nozzle of PWR fuel assembly | |
| JPS629688B2 (en) | ||
| JPH0342637B2 (en) | ||
| US4113562A (en) | Apparatus for controlling coolant level in a liquid-metal-cooled nuclear reactor | |
| JP2000292578A (en) | Steam-condensing device in storage container | |
| JPS5824981Y2 (en) | offshore work platform | |
| JPS60158385A (en) | Spray tube for reactor housing vessel | |
| JPH10129580A (en) | Semisubmergible offshore structure supported by hollow floating bag | |
| JPS61223583A (en) | Bent tube |