JPS5815193A - Supporting device of reactor shroud - Google Patents

Supporting device of reactor shroud

Info

Publication number
JPS5815193A
JPS5815193A JP56113502A JP11350281A JPS5815193A JP S5815193 A JPS5815193 A JP S5815193A JP 56113502 A JP56113502 A JP 56113502A JP 11350281 A JP11350281 A JP 11350281A JP S5815193 A JPS5815193 A JP S5815193A
Authority
JP
Japan
Prior art keywords
shroud
pressure vessel
bracket
long groove
fixed
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
Application number
JP56113502A
Other languages
Japanese (ja)
Inventor
師 弘之
茂樹 辻
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP56113502A priority Critical patent/JPS5815193A/en
Publication of JPS5815193A publication Critical patent/JPS5815193A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Exhaust Gas After Treatment (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】 この発明は、定置された原子炉圧力容器中に原子炉炉心
の外壁をなすシュラウドを支持する原子炉シュラウドの
支持装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a reactor shroud support device that supports a shroud forming an outer wall of a nuclear reactor core in a stationary nuclear reactor pressure vessel.

従来の原子炉シュ2クド(以下単にシュラウドと称する
)支持装置は、上端が炉心の外壁をなすシュ2ウドの底
面周辺に固着され、下端が原子炉圧力容器(以下単に圧
力容器と称する)の内庭部に固着された柱状又は円筒状
に配設され九シェラウド支持脚からなっている。
A conventional reactor shroud (hereinafter simply referred to as shroud) support device is fixed around the bottom of the shroud whose upper end forms the outer wall of the reactor core, and whose lower end forms the reactor pressure vessel (hereinafter simply referred to as pressure vessel). It consists of nine shell support legs arranged in a columnar or cylindrical shape fixed to the inner court.

前記従来のシェラウド支持装置にあっては、炉心構造物
の重量はすべてシェラウド支持脚で支承され、シュ2ク
ドの上方部には支持部がないため、地震時にはシュラウ
ド上部がシュラウド支持脚の部に大きい曲げ応力が生ず
る處れがありた。
In the conventional shroud support device, all the weight of the core structure is supported by the shroud support legs, and there is no support part in the upper part of the shroud. Therefore, in the event of an earthquake, the upper part of the shroud is supported by the shroud support legs. There was a risk that large bending stress would occur.

この発明は、従来のシュラウド支持装置の前記欠点を除
き又は軽減するためになされたもので。
The present invention has been made to eliminate or alleviate the drawbacks of conventional shroud support devices.

地震時におけるいかなる水平方向の荷重に対しても前記
圧力容器とシュラウドとの水平方向相対変位を拘束する
ことによ)シュラウドの横振れ振動を抑制し、その横振
れ振動に基づく応力発生を減少せしめると共に、原子炉
運転時はシュラクトと圧力容器との温度差によって生じ
る半径方向および上下方向の相対変位を吸収することが
可能なシュラウド支持装置を提供することを目的として
いるO この発明の一実施例を添付の図面により説明する。
By restraining the horizontal relative displacement between the pressure vessel and the shroud against any horizontal load during an earthquake, the lateral vibration of the shroud is suppressed, and stress generation due to the lateral vibration is reduced. In addition, it is an object of the present invention to provide a shroud support device capable of absorbing relative displacement in the radial direction and vertical direction caused by the temperature difference between the shroud and the pressure vessel during nuclear reactor operation. will be explained with reference to the attached drawings.

l@1図において、直立リング状のシェラウド支持脚1
はその上端を炉心2の外周壁をなすシュ2ウド3の底部
5の周辺に溶接固着され、その下端を定置された圧力容
器4の内底面に溶接固着されている。ま友、補強リブ6
はその内端を前記シュ2ウド3の底部5に溶接固着され
、その外端を圧力容器4の内壁に溶接固着されている。
l@1 In the figure, the upright ring-shaped shellaud support leg 1
Its upper end is welded and fixed around the bottom part 5 of the shroud 3 forming the outer peripheral wall of the reactor core 2, and its lower end is welded and fixed to the inner bottom surface of the fixed pressure vessel 4. Mayu, reinforcement rib 6
Its inner end is welded and fixed to the bottom 5 of the shroud 3, and its outer end is welded and fixed to the inner wall of the pressure vessel 4.

複数組の支持構造体7は、それぞれの水平中心軸線をシ
ュ2ウド3、圧力容器4の半径線上に置いて、シュラウ
ド3の上端に近く、シュラウド3の外周と圧力容器4の
内周間の対向する位置に相互に間隔をあけて放射状に、
円周上等ピツチに、水平に配設されている。
The plurality of sets of support structures 7 are arranged so that their respective horizontal center axes are placed on the radial line of the shroud 3 and the pressure vessel 4, and are located near the upper end of the shroud 3 and between the outer periphery of the shroud 3 and the inner periphery of the pressure vessel 4. radially in opposing positions and spaced apart from each other;
They are arranged horizontally at equal pitches around the circumference.

第2因、第3図において、支持構造体7は、シュラウド
3の外周に直角且つ水平に内端面が固着され、外端面が
圧力容器4の内周から隔離されている第一ブラケット8
と、圧力容器4の内周の第一ブラケット8と対向する位
置に直角且つ水平にして上面を第一ブラケット8の下面
に接近させ、内端面がシュラウド3の外周面から隔離さ
れて、圧力容器4の内周に外端面が固着されている第ニ
ブラケット9とを一組として備えている。
The second factor, in FIG. 3, the support structure 7 includes a first bracket 8 whose inner end surface is fixed perpendicularly and horizontally to the outer periphery of the shroud 3, and whose outer end surface is isolated from the inner periphery of the pressure vessel 4.
The upper surface of the pressure vessel 4 is placed perpendicularly and horizontally to the position facing the first bracket 8 on the inner circumference of the pressure vessel 4, and its upper surface approaches the lower surface of the first bracket 8, and the inner end surface is isolated from the outer circumferential surface of the shroud 3. A second bracket 9 whose outer end surface is fixed to the inner periphery of the bracket 4 is provided as a set.

第ニブラケット9の上面には、その水平中心軸線に沿っ
て、内端部が開放されこれと反対側の熾が半円形をなす
長みぞ10が掘り込まれており。
A long groove 10 is dug into the upper surface of the second bracket 9 along its horizontal central axis, and the inner end is open and the opposite side is semicircular.

長みぞlO中に偏心ピン軸11の長みぞlOの幅よシ小
さい直径を有する円柱部11aがはめ込まれている。偏
心ピン軸11の上方部は1円柱部11mよシ小さな直径
にして円柱部11mと偏心した軸部11bとな夛、軸°
部11bは第一ブラケット8を垂直に貫通しそれと静合
している。軸部11bの上端面中心には図示しない六角
穴が設けられている。
A cylindrical portion 11a having a diameter smaller than the width of the long groove 1O of the eccentric pin shaft 11 is fitted into the long groove 1O. The upper part of the eccentric pin shaft 11 has a smaller diameter than the cylindrical part 11m, and has a cylindrical part 11m and an eccentric shaft part 11b.
The portion 11b vertically passes through the first bracket 8 and is statically engaged therewith. A hexagonal hole (not shown) is provided at the center of the upper end surface of the shaft portion 11b.

シ:L2ウド3の圧力容器4内へのす見付方法は次の通
〕である。
B: The method for finding the L2 cloud 3 in the pressure vessel 4 is as follows.

偏心ピン軸11の円柱部11aが第ニブラケット9の長
みぞ1G(2)11面に触れない状mまで図示しない工
具で偏心ピン軸11を回した後、シュ2ウド3をシェラ
ウド支持脚1上に載置して溶接固定する。次に、偏心ピ
ン軸11の軸部11bを前記工具によって回転させる。
After turning the eccentric pin shaft 11 with a tool (not shown) until the cylindrical portion 11a of the eccentric pin shaft 11 does not touch the long groove 1G (2) 11 surface of the second bracket 9, the shroud 3 is attached to the shroud support leg 1. Place it on top and weld it in place. Next, the shaft portion 11b of the eccentric pin shaft 11 is rotated using the tool.

この場合1円柱部11 aFi第ニブラケット9の長み
ぞ10内で回転するが、軸部11bと円柱部11mとは
偏心しているので円柱部11aの外周は長みぞ10の一
側面に接触して停止する(第3図)。この位置で軸部1
1bの上端外周を第一ブラケット8の上面に溶接し偏心
ピン軸11を第一ブラケット8に固定する。
In this case, the first cylindrical part 11 aFi rotates within the long groove 10 of the second bracket 9, but since the shaft part 11b and the cylindrical part 11m are eccentric, the outer periphery of the cylindrical part 11a contacts one side of the long groove 10. Stop (Figure 3). At this position, the shaft part 1
The outer circumference of the upper end of 1b is welded to the upper surface of the first bracket 8, and the eccentric pin shaft 11 is fixed to the first bracket 8.

(5) この支持構造体7の組数は4組または8組にしてこれら
のそれぞれがシュラクト3の外周圧力容器4の内周に沿
い円周方向等ピッチに配設されている。また、偏心ビン
軸110円柱部1゛1aと第ニブラケット9の長みぞ1
0の一側面に接触する位置は、地震などの外力の方向性
を考慮して決定する必要がある。第4図社4組の支持構
造体7のそれぞれを示す7人ないし7Dを直交する水平
直径線上にそれぞれ対向して配設した場合を例示し喪も
のであるが、この場合の円柱部11mと長みぞ10の接
触位置線図示の通シとなっている。すなわち、支持構造
体7人では前記接触位置は圧力容器4の中心軸線に向っ
て長みぞ10の右側であり、7Bでは左側、7Cでは右
側%7Dでは左側となっている。
(5) The number of supporting structures 7 is 4 or 8, and each of these is arranged at equal pitches in the circumferential direction along the inner periphery of the outer pressure vessel 4 of the shracto 3. In addition, the eccentric bottle shaft 110 cylindrical portion 1'1a and the second bracket 9 long groove 1
The position of contact with one side of 0 needs to be determined in consideration of the directionality of external forces such as earthquakes. Figure 4 shows a case in which 7 members or 7D representing each of the four sets of support structures 7 are arranged facing each other on orthogonal horizontal diameter lines, but in this case the columnar part 11m and The contact position line of the long groove 10 is shown in the drawing. That is, in the case of seven supporting structures, the contact position is on the right side of the long groove 10 toward the central axis of the pressure vessel 4, and is on the left side in 7B, on the right side in 7C, and on the left side in 7D.

この発明による前記シュラウド支持装置の作用を次に説
明する。
The operation of the shroud support device according to the present invention will now be described.

内部構造物を含む大重量の炉心2は、その重量を7ユラ
ウド3を介しシュラウド支持構4で支承される。シュラ
ウド3は、その上端近くで、放射(6) 状且9水千′配設2t′″た複数組0支持構造体7Kc
より圧力容器4に支承されていて、支持構造体7の第一
ブラケット8に固定され九偏心ビ/軸11の円柱部11
aが第ニブラケット9の長みぞ10内の一側面に接触し
ているので、地震によるいかなる方向の水平外力を受け
た場合においても、この荷重による圧力容器4とシュラ
ウド3とめ水平方向相対変位を拘束すると七ができるの
で、シェフウド3の上方部が下方部に対し横振れしよう
としても前記支持構造体7の抑制作用によって直立状態
が維持される。今、この抑制作用を第4図により説明す
ると1例えば、X方向の地震力による相対変位に対して
は支持構造体7Cおよび7Dが協同して拘束する。これ
と同様に ’X1方向にはテゞルに、7Bが、″!九Y
方向には7B、7Cが、さらにY′方向には7A%7D
がそれぞれ拘束する。
The heavy reactor core 2 including internal structures is supported by a shroud support structure 4 via a seven-wheeled roof 3 . Near its upper end, the shroud 3 has a plurality of support structures 7Kc arranged in a radial (6) shape and arranged 2t'''.
The cylindrical part 11 of the shaft 11 is supported by the pressure vessel 4 and fixed to the first bracket 8 of the support structure 7.
Since point a is in contact with one side of the long groove 10 of the second bracket 9, even if a horizontal external force is applied in any direction due to an earthquake, the pressure vessel 4 and shroud 3 will not be displaced horizontally by this load. When restrained, 7 is formed, so even if the upper part of the chef's window 3 tries to sway laterally with respect to the lower part, the upright state is maintained by the restraining action of the support structure 7. This restraining action will now be explained with reference to FIG. 4. For example, the support structures 7C and 7D cooperate to restrain relative displacement due to an earthquake force in the X direction. Similarly, in the X1 direction, 7B is on the tail, ``!9Y
7B and 7C in the direction, and 7A%7D in the Y' direction
are each constrained.

シュラウド8が炉心2内の核燃料の作用によシ温度が上
昇して半径方向に熱膨張しても、偏心ピン軸11の円柱
部11aが長みぞ10内をその長さ方向に自由に滑動す
るので熱膨張を吸収することができると共に、シュラウ
ド3は、その上下方向の熱膨張に対しても、第一ブラケ
ット8が上方に対し全く自由に変位できるので何等拘束
を受けることはない。
Even if the temperature of the shroud 8 increases due to the action of the nuclear fuel in the core 2 and thermally expands in the radial direction, the cylindrical portion 11a of the eccentric pin shaft 11 freely slides in the longitudinal direction within the long groove 10. Therefore, the shroud 3 can absorb thermal expansion, and the shroud 3 is not constrained in any way by the vertical thermal expansion since the first bracket 8 can be completely freely displaced upwardly.

この発明によるシュラウド支持装置は、その実施例につ
いて前記に詳述したように、炉心の外壁部をなすシュラ
ウドの外底部に上端が固着され。
The shroud support device according to the present invention has its upper end fixed to the outer bottom of the shroud forming the outer wall of the reactor core, as described in detail above.

下端が炉心を収納する圧力容器の内底部に固着されたシ
ュ2ウド支持脚と、シュラウドの上端近くにシュラウド
の外周と圧力容器内周間に放射状且つ水平に配設され、
シュラウドを圧力容器に対しその半径方向および軸線方
向滑動自在に且つ円周方向変位を拘束して支持する第一
ブラケットおよび第ニブラケットならびに偏心ピン軸よ
りなる複数組の支持構造体とを備え九構成となし、地震
時のいかなる方向の水平外力に対してもこの荷重による
圧力容器とシュラウドとの水平方向相対変位を拘束する
ことによ〕、シュラウドの横振れ振動を防止し、この振
動に基づく支持構成部(応力が生ずることを防ぎ、更に
炉心内の核燃料の発生熱に基づく7ユラウドの熱#脹に
も対応できる効果がある。また、前記支持構造体の構成
よりして。
A shroud support leg whose lower end is fixed to the inner bottom of the pressure vessel housing the reactor core, and a shroud support leg disposed near the upper end of the shroud radially and horizontally between the outer periphery of the shroud and the inner periphery of the pressure vessel,
The support structure includes a first bracket, a second bracket, and a plurality of sets of eccentric pin shafts that support the shroud so as to be slidable in the radial and axial directions with respect to the pressure vessel while restraining displacement in the circumferential direction. By restraining horizontal relative displacement between the pressure vessel and the shroud due to this load against horizontal external forces in any direction during an earthquake, lateral vibration of the shroud is prevented, and support based on this vibration is prevented. It has the effect of preventing the generation of stress in the structural parts and also being able to cope with the heat expansion of 7 Euros due to the heat generated by the nuclear fuel in the reactor core.Also, due to the structure of the support structure.

シュラウドと圧力容器の取付誤差を吸収できるので、す
え付時の合せ加工を省略できる効果も併せ有する。
Since it is possible to absorb installation errors between the shroud and the pressure vessel, it also has the effect of omitting the alignment process when installing the shroud.

【図面の簡単な説明】[Brief explanation of drawings]

第1図はこの発明による原子炉シュラウドの支持装置が
装着された原子炉圧力容器の縦断面図。 第2図は第1図の支持構造体7の拡大縦断面図。 第3図は第2図の曹−■断面における断面図、第4図は
第2図、第3図における偏心ピン軸11と長穴10との
関係位置図である。 1・・・支持脚、2・・・原子炉炉心%3・・・原子炉
シュラウド、4・・・原子炉圧力容器、7・・・支持構
造体。 8・・・第一プツケット、9・・・第ニブラケット、1
0・・・長みぞ、11・・・偏心ピン軸 (7317)  代理人  弁理士 則近憲佑(ほか1
名) (9)
FIG. 1 is a longitudinal sectional view of a reactor pressure vessel equipped with a reactor shroud support device according to the present invention. FIG. 2 is an enlarged longitudinal sectional view of the support structure 7 of FIG. 1. 3 is a cross-sectional view taken along the line II in FIG. 2, and FIG. 4 is a diagram showing the relationship between the eccentric pin shaft 11 and the elongated hole 10 in FIGS. 2 and 3. DESCRIPTION OF SYMBOLS 1...Support leg, 2...Reactor core %3...Reactor shroud, 4...Reactor pressure vessel, 7...Support structure. 8...First putzket, 9...Second bracket, 1
0...Long groove, 11...Eccentric pin shaft (7317) Agent: Patent attorney Kensuke Norichika (and 1 others)
name) (9)

Claims (1)

【特許請求の範囲】 原子炉炉心の外壁をなすシェラウドの外底部に上端が固
着され原子炉圧力容器の内底部に下端が固着され九支持
脚と、前記シュ2ウドの上端近くシェラウドの外周と前
記圧力容器の内周間の対向する位置に水平且つ放射状に
して相互に広い間隔をあけて配設された複数組の支持構
造体とを備え。 この支持構造体が、前記シェラウドの外周に直角且つ水
平に内端面が固着され外端面が前記圧力容器の内周から
隔離されている第一ブラケットと。 前記圧力容器の内周に直角且つ水平にして上面を前記第
一プラケットの下面に接近させ内端面が前記シュラウド
の外周から隔離されて圧力容器の内周に外端面が固着さ
れ且つ上面にシ、3−2ウドの半径線上に長みぞを有す
る第ニブラケットと、下端に前記長みぞの幅よシ小さい
直径にして外周が長みぞの側壁の一方に接して長みぞ中
にはt、b込む偏心円柱部を有し前記第一ブラケットに
上方軸部において固着された偏心ビン軸とからなる原子
炉シュ2ウドの支持装置。
[Scope of Claims] Nine support legs having an upper end fixed to the outer bottom of the shroud forming the outer wall of the reactor core and a lower end fixed to the inner bottom of the reactor pressure vessel; and a plurality of sets of support structures disposed horizontally and radially at wide intervals from each other at opposing positions between the inner peripheries of the pressure vessel. a first bracket, wherein the support structure has an inner end surface fixed perpendicularly and horizontally to the outer periphery of the sheroud, and an outer end surface separated from the inner periphery of the pressure vessel; The upper surface is perpendicular and horizontal to the inner periphery of the pressure vessel, the upper surface approaches the lower surface of the first shroud, the inner end surface is isolated from the outer periphery of the shroud, the outer end surface is fixed to the inner periphery of the pressure vessel, and 3-2 A second bracket having a long groove on the radius line of the rod, and a second bracket having a diameter smaller than the width of the long groove at the lower end, the outer periphery touches one of the side walls of the long groove, and T and B are inserted into the long groove. A support device for a nuclear reactor shroud comprising an eccentric cylinder shaft having an eccentric cylindrical portion and an eccentric bottle shaft fixed to the first bracket at an upper shaft portion.
JP56113502A 1981-07-22 1981-07-22 Supporting device of reactor shroud Pending JPS5815193A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56113502A JPS5815193A (en) 1981-07-22 1981-07-22 Supporting device of reactor shroud

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56113502A JPS5815193A (en) 1981-07-22 1981-07-22 Supporting device of reactor shroud

Publications (1)

Publication Number Publication Date
JPS5815193A true JPS5815193A (en) 1983-01-28

Family

ID=14613943

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56113502A Pending JPS5815193A (en) 1981-07-22 1981-07-22 Supporting device of reactor shroud

Country Status (1)

Country Link
JP (1) JPS5815193A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5313074A (en) * 1990-05-31 1994-05-17 Osaka Gas Company Limited Josephson device formed over a recess step with protective layer
JP2007502425A (en) * 2003-08-15 2007-02-08 ぺブル ベッド モジュラー リアクター (プロプリエタリー)リミテッド Support device

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5313074A (en) * 1990-05-31 1994-05-17 Osaka Gas Company Limited Josephson device formed over a recess step with protective layer
JP2007502425A (en) * 2003-08-15 2007-02-08 ぺブル ベッド モジュラー リアクター (プロプリエタリー)リミテッド Support device

Similar Documents

Publication Publication Date Title
JPS5837493A (en) Heat exchanger
JPS5815193A (en) Supporting device of reactor shroud
JPS607388A (en) Supporter for nuclear reactor containing vessel
JPS604159Y2 (en) Support device for torus type fusion device
JP2025168740A (en) Support structure for vertically placed cylindrical containers
JPH08233985A (en) Storage facility for spent nuclear fuel
JPS5811688A (en) Earthquake-proof supporting structure of vessel
JPH057597Y2 (en)
JPS63114775A (en) Earthquakeproof damper
JPS58150893A (en) Vented support structure
JPS6247024Y2 (en)
JPH0410999B2 (en)
KR20250149386A (en) Nuclear power plant having improved safety for earthquake using spring sturucture
JPS61139794A (en) Earthquake-proof support structure of reactor vessel
JPS60222793A (en) reactor structure
JPS6058382A (en) Earthquakeproof support structure of variable temperature vessel
JPS61105386A (en) Piping pipe group support structure
JPS6220518B2 (en)
JPS60162988A (en) Earthquakeproof support structure of high-temperature apparatus
JPH0432358B2 (en)
JPS6086487A (en) Upper section supporter for pressure vessel of nuclear reactor
JPS6040884A (en) Earthquake response type piping earthquakeproof support
JPH0138280B2 (en)
JPS6346392B2 (en)
JPS61118690A (en) Hanging drum of core for nuclear reactor