JPS6331079B2 - - Google Patents

Info

Publication number
JPS6331079B2
JPS6331079B2 JP55182987A JP18298780A JPS6331079B2 JP S6331079 B2 JPS6331079 B2 JP S6331079B2 JP 55182987 A JP55182987 A JP 55182987A JP 18298780 A JP18298780 A JP 18298780A JP S6331079 B2 JPS6331079 B2 JP S6331079B2
Authority
JP
Japan
Prior art keywords
storage frame
frame according
tubes
tube
storage
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
Application number
JP55182987A
Other languages
Japanese (ja)
Other versions
JPS57125891A (en
Inventor
Kuriigaa Furiitorihi
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.)
GEORUKU NOERU GmbH
Original Assignee
GEORUKU NOERU GmbH
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 GEORUKU NOERU GmbH filed Critical GEORUKU NOERU GmbH
Priority to JP55182987A priority Critical patent/JPS57125891A/en
Publication of JPS57125891A publication Critical patent/JPS57125891A/en
Publication of JPS6331079B2 publication Critical patent/JPS6331079B2/ja
Granted 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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は、原子力発電所からの使用済み燃料要
素用貯蔵架台であつて、多数の管から成つてお
り、該管が長方形又は正方形の横断面を有しかつ
燃料要素を収容するための1つ以上の室を有する
形式のものに関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention is a storage cradle for spent fuel elements from a nuclear power plant, which consists of a number of tubes, the tubes having a rectangular or square cross section and a storage frame for spent fuel elements from a nuclear power plant. of the type having one or more chambers for accommodating.

西ドイツ国特許出願公開第2730850号明細書か
ら貯蔵架台が公知である。この場合には個々の管
が下側に切欠きを有するねじ付きピンを有してお
り、該ピンが貯蔵プールの底に固定された球セグ
メント上に支承されている。例えば地震の際に生
じるような水平方向の衝撃において、個々の管に
作用する傾動モーメントを吸収するために、隣接
した管の脚板はユニツト、即ち貯蔵架台に結合さ
れている。このようにして、個々の脚板から組立
てられた大きな剛性板が形成される。従つて水平
方向の衝撃によつて生ぜしめられる加速力は貯蔵
架台を球セグメントによつて持上げることができ
ない。この形式の貯蔵架台の構造は、個々の管の
結合を、貯蔵プールに挿入する前又は後に行なう
ことを必要とする。先に結合する場合には、もは
や搬送不能である貯蔵架台が製作される従つて比
較的小さなユニツトが製造され、該ユニツトが貯
蔵プールに沈められた後そこで結合される。しか
しこの処略は貯蔵プールが高くなると極めて困難
である、特にこの位置でのねじ締めが不十分であ
れば水平方向の衝撃において折曲りが生じる。
A storage frame is known from DE 27 30 850 A1. In this case, each tube has a threaded pin with a cutout on the underside, which pin is supported on a ball segment fixed to the bottom of the storage pool. In order to absorb the tilting moments acting on the individual tubes in the case of horizontal shocks, such as occur, for example, during earthquakes, the legs of adjacent tubes are connected to a unit or storage cradle. In this way, a large rigid plate assembled from individual leg plates is formed. Acceleration forces caused by horizontal impacts therefore cannot lift the storage pedestal by the ball segments. This type of storage cradle construction requires that the individual tubes be joined either before or after insertion into the storage pool. In the case of first joining, a storage cradle is produced which can no longer be transported, so that relatively small units are produced which are submerged in a storage pool and then joined there. However, this procedure is extremely difficult when the storage pool is high, especially if the screws are insufficiently tightened at this location, bending will occur on horizontal impacts.

本発明の課題は、冒頭に述べた形式の貯蔵架台
において夫々個々の管が水平方向の衝撃に対して
安全であり、しかも貯蔵プール内の所定の錠止が
単に沈降部材を有する管の重量によつて行なわれ
かつ管の取外しの際に自動的に解錠されるように
構成することであつた。
The object of the invention is to provide a storage frame of the type mentioned at the outset, in which each individual tube is safe against horizontal impacts, and in which the defined locks in the storage pool are only limited by the weight of the tubes with settling elements. Therefore, the lock is automatically unlocked when the pipe is removed.

この課題は、夫々の管が少なくとも3つの水平
なピンを有しており、該ピンの中心軸が点内交差
しかつ貯蔵プールの底にピンに配属された脚板が
固定されており、該脚板の側壁が斜めの切欠きを
有し、該切欠きが上方に向つてくさび形に拡開さ
れており、上記管の沈降位置で切欠きを貫通する
中心軸がボルトを貫通する中心軸と一致するよう
に構成することにより解決される。
The problem is that each tube has at least three horizontal pins, the central axes of which intersect in a point, and a leg plate assigned to the pins is fixed at the bottom of the storage pool, and the leg plates are fixed at the bottom of the storage pool. The side wall of the pipe has a diagonal notch, the notch widens upward into a wedge shape, and the central axis passing through the notch at the submerged position of the pipe coincides with the central axis passing through the bolt. This can be solved by configuring it so that

次に、図示の実施例につき本発明を詳細に説明
する。
The invention will now be explained in detail with reference to the illustrated embodiments.

貯蔵架台1は、長方形又は正方形の横断面を有
する多数の管2から構成され、この場合管2は
個々の使用済み燃料要素を収容するため或は第1
図に示されているように多数の室3に分割するこ
とによつて相応する数の燃料要素を収容するため
に構成されていてもよい。この場合、室3の横断
面は燃料要素の外寸に合わされている。
The storage pedestal 1 consists of a number of tubes 2 with a rectangular or square cross-section, in which case the tubes 2 are used for accommodating individual spent fuel elements or
It may be arranged to accommodate a corresponding number of fuel elements by dividing it into a number of chambers 3 as shown in the figures. In this case, the cross section of the chamber 3 is adapted to the external dimensions of the fuel element.

貯蔵架台1は、原子炉から取出した後、再処理
設備に装入する前に、なお一定の減衰段階を必要
とする燃料要素の中間貯蔵のために使用すること
ができる。それと共に、この架台は燃料要素を再
処理するまで、供給された燃料要素を貯蔵するた
めに、再処理設備自体のためにも好適である。
The storage pedestal 1 can be used for intermediate storage of fuel elements which still require a certain decay stage after removal from the reactor and before loading into a reprocessing facility. In addition, this cradle is also suitable for the reprocessing plant itself, in order to store the supplied fuel elements until they are reprocessed.

管2は下側で板4によつて被われており、該板
は室3に通じる孔5を有している従つて冷却水は
夫々の室3内の燃料要素に達することができる。
板4の下には、少なくとも3つ、第1図の場合に
は4つのピン6が固定されており、該ピンの中心
軸aはほぼ点Mで交差する、この場合全てのピン
6の端面は点Mに対して同じ間隔を有する。水平
方向の衝撃において傾到モーメントを吸収するた
めにできるだけ大きな土台を得るために、この実
施例においてはピン6は対角線方向で管2の角の
範囲に配置されている。
The tubes 2 are covered on the lower side by a plate 4 which has holes 5 leading into the chambers 3 so that the cooling water can reach the fuel elements in the respective chambers 3.
At least three pins 6, four in the case of FIG. have the same spacing with respect to point M. In order to obtain as large a base as possible for absorbing tilting moments in the case of horizontal impacts, in this embodiment the pins 6 are arranged diagonally in the area of the corners of the tube 2.

貯蔵プールの底上では、第1図に示されている
ように、収容されるべき管の数に相応して、4角
形の脚板7が上方に突出した側壁8と固定されて
いる、この場合側壁8は平面図で見て長方形又は
正方形を形成しかつ有利には側方半割中心線は中
心軸aの軸線延長部を形成する。夫夫の側壁8は
傾めのかつ更に上方に開いた切欠き9を有し、該
切欠きはくさび形に拡開されている。しかもくさ
び面10及び11はピン6のための案内機構とし
て動く。この場合、切欠き9内でのできるだけ強
制力の無い案内及び遊びの無い支承を行なうため
に、切欠き9の直径は収容されるべきピン6の横
断面に一致する。
On the bottom of the storage pool, as shown in FIG. 1, a square leg plate 7 is fixed with upwardly projecting side walls 8, corresponding to the number of tubes to be accommodated, in this case The side walls 8 form a rectangle or a square in plan view and the lateral half center lines advantageously form an axial extension of the central axis a. The side wall 8 of the husband has an inclined and further upwardly opening notch 9, which is widened in the shape of a wedge. Moreover, the wedge surfaces 10 and 11 act as a guide mechanism for the pin 6. In this case, the diameter of the recess 9 corresponds to the cross section of the pin 6 to be accommodated, in order to achieve as free a guidance and a play-free bearing in the recess 9 as possible.

管2は公知方法でホイストによつて貯蔵プール
内に沈められる、この場合夫々のピン6は管2の
重量と、くさび面10又は11によつて同時に回
転運動しながら側壁8の所属の切欠き9に嵌合し
かつ該切欠き内でくさび面10によつて形成され
た突起12によつて垂直方向で持上らないように
保持される。この場合、側壁8は平らであるか又
は点Mを中心とした設置円に相応して内側に向つ
て湾曲せしめられていてもよい。管2の重量から
の垂直方向の力並びに脚板上への水平方向の衝撃
からの加速力は、ピン6を介して脚板7に伝達さ
れる。第1図から明らかなように、夫々の管2に
は4つの脚板7が配属されており、この場合夫々
の脚板は4つの管2を錠止するために構成されて
いる。
The tube 2 is lowered into the storage pool by means of a hoist in a known manner, in which case the respective pin 6 is driven by the weight of the tube 2 and the corresponding recess in the side wall 8 with simultaneous rotational movement by means of the wedge surface 10 or 11. 9 and is held against lifting in the vertical direction by a projection 12 formed by a wedge surface 10 in the recess. In this case, the side walls 8 can be flat or curved inwardly, corresponding to the installation circle around the point M. Vertical forces from the weight of the tube 2 as well as acceleration forces from horizontal impacts on the leg plate are transmitted to the leg plate 7 via the pins 6. As can be seen in FIG. 1, four leg plates 7 are assigned to each tube 2, each leg plate being designed for locking four tubes 2.

第3図には、管2を収容するための円形の脚板
が示されており、該脚板は管2からの垂直方向の
力を貯蔵プールの底に伝達するための対応受とし
て形成されている。円形側壁8は点Mを中心とし
た設置円と一致しかつ前記形式の切欠き9を有す
る。この場合、ピン6は専ら加速力を伝達する。
FIG. 3 shows a circular foot plate for accommodating the tube 2, which foot plate is formed as a counter for transmitting the vertical force from the tube 2 to the bottom of the storage pool. . The circular side wall 8 coincides with the installation circle centered on the point M and has a cutout 9 of the type described above. In this case, pin 6 exclusively transmits acceleration forces.

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

図面は本発明の実施例を示し、第1図は、第1
実施例の水平断面図、第2図は、第1図の−
線に沿つた断面図及び第3図は、第2実施例の水
平断面図である。 2……管、3……室、4……板、5……開口、
6……ピン、7……脚板、8……側壁、9……切
欠き、10,11……くさび面、12……突起、
a……中心軸、M……点。
The drawings show embodiments of the invention, and FIG.
The horizontal sectional view of the embodiment, FIG.
A cross-sectional view along the line and FIG. 3 are horizontal cross-sectional views of the second embodiment. 2...Pipe, 3...Chamber, 4...Plate, 5...Opening,
6... Pin, 7... Leg plate, 8... Side wall, 9... Notch, 10, 11... Wedge surface, 12... Protrusion,
a... Central axis, M... point.

Claims (1)

【特許請求の範囲】 1 原子力発電所からの使用済み燃料要素用貯蔵
架台であつて、多数の管から成つており、該管が
長方形又は正方形の横断面を有しかつ燃料要素を
収容するための1つ以上の室を有する形式のもの
において、夫々の管2が少なくとも3つの水平な
ピン6を有しており、該ピンの中心軸aが点Mで
交差しかつ貯蔵プールの底にピン6に配属された
脚板7が固定されており、該脚板の側壁8が斜め
の切欠き9を有し、該切欠きが上方に向つてくさ
び形に拡開されており、上記管2の沈降位置で切
欠きを貫通する中心軸がボルト6を貫通する中心
軸aと一致するように構成されていることを特徴
とする、原子力発電所からの使用済み燃料要素用
貯蔵架台。 2 切欠き9が上方に向つてくさび形に拡開され
ておりかつくさび面10及び11がピン6のため
の案内機構を形成する、特許請求の範囲第1項記
載の貯蔵架台。 3 切欠き9の直径がピン6の直径に等しい、特
許請求の範囲第1項又は第2項記載の貯蔵架台。 4 管2が下側で板4によつて被われており、該
板がピン6を有しかつ管2内の室3に通じる開口
5を有する、特許請求の範囲第1項記載の貯蔵架
台。 5 管2のピン6の端面が点Mに対して同じ間隔
を有する、特許請求の範囲第1項〜第4項のいず
れか1項に記載の貯蔵架台。 6 ピン6が対角線方向で管2の角の範囲に配置
されている、特許請求の範囲第5項記載の貯蔵架
台。 7 切欠き9の上方壁及びくさび面10によつて
突起12が形成されており、該突起がピン6を切
欠き内での貯蔵状態で少なくとも垂直な中心面ま
で被う、特許請求の範囲第2項記載の貯蔵架台。 8 側壁8が平面図で見て脚板7上に長方形又は
正方形を形成しかつ側方半割中心線が中心軸aの
軸線延長部を形成するように貯蔵架台の底上に固
定されている、特許請求の範囲第1項記載の貯蔵
架台。 9 夫々の管2に4つの脚板7が配属されており
かつ脚板上での管の支承及び確保がピン6のみを
介して行なわれる、特許請求の範囲第1項記載の
貯蔵架台。 10 夫々の管2にリング状脚板7が配属されて
おり、該脚板の円形のかつ点Mを中心した設置円
と一致する側壁8が取付けられたピン6の数に相
応して切欠き9を有している、特許請求の範囲第
1項記載の貯蔵架台。 11 管2が板4のみで脚板7上に支承されてい
る、特許請求の範囲第10項記載の貯蔵架台。
[Scope of Claims] 1. A storage frame for spent fuel elements from a nuclear power plant, consisting of a number of tubes, the tubes having a rectangular or square cross section and for accommodating fuel elements. of the type with one or more chambers, each tube 2 has at least three horizontal pins 6 whose central axes a intersect at a point M and which are attached to the bottom of the storage pool. A leg plate 7 assigned to 6 is fixed, the side wall 8 of said leg plate having an oblique notch 9 which widens upward in the form of a wedge, and which prevents the settling of said tube 2. A storage frame for spent fuel elements from a nuclear power plant, characterized in that the central axis passing through the notch coincides with the central axis a passing through the bolt 6 at a position. 2. Storage rack according to claim 1, wherein the cutout 9 widens upward in the form of a wedge and the wedge surfaces 10 and 11 form a guide mechanism for the pin 6. 3. The storage frame according to claim 1 or 2, wherein the diameter of the notch 9 is equal to the diameter of the pin 6. 4. Storage frame according to claim 1, in which the tube 2 is covered on the underside by a plate 4, which plate has a pin 6 and has an opening 5 leading to a chamber 3 in the tube 2. . 5. The storage frame according to any one of claims 1 to 4, wherein the end faces of the pins 6 of the tubes 2 have the same distance from the point M. 6. Storage frame according to claim 5, in which the pins 6 are arranged diagonally in the area of the corners of the tubes 2. 7 The upper wall of the recess 9 and the wedge surface 10 form a protrusion 12 which covers the pin 6 in the state of storage in the recess at least up to the vertical central plane. The storage frame according to item 2. 8. The side walls 8 form a rectangle or square on the leg plate 7 in plan view and are fixed on the bottom of the storage frame in such a way that the lateral half-center lines form an axial extension of the central axis a; A storage frame according to claim 1. 9. Storage rack according to claim 1, in which each tube 2 is assigned four leg plates 7, and the tubes are supported and secured on the leg plates only via pins 6. 10 A ring-shaped leg plate 7 is assigned to each tube 2, and a side wall 8 of the leg plate, which is circular and coincides with the installation circle centered on the point M, has cutouts 9 corresponding to the number of pins 6 attached thereto. A storage frame according to claim 1, comprising: a storage frame according to claim 1; 11. Storage frame according to claim 10, in which the tubes 2 are supported on the leg plates 7 only by the plates 4.
JP55182987A 1980-12-25 1980-12-25 Storage rack for spent fuel element from atomic power plant Granted JPS57125891A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP55182987A JPS57125891A (en) 1980-12-25 1980-12-25 Storage rack for spent fuel element from atomic power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP55182987A JPS57125891A (en) 1980-12-25 1980-12-25 Storage rack for spent fuel element from atomic power plant

Publications (2)

Publication Number Publication Date
JPS57125891A JPS57125891A (en) 1982-08-05
JPS6331079B2 true JPS6331079B2 (en) 1988-06-22

Family

ID=16127774

Family Applications (1)

Application Number Title Priority Date Filing Date
JP55182987A Granted JPS57125891A (en) 1980-12-25 1980-12-25 Storage rack for spent fuel element from atomic power plant

Country Status (1)

Country Link
JP (1) JPS57125891A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0580435U (en) * 1992-07-15 1993-11-02 タイガー魔法瓶株式会社 Pump injection type liquid container

Also Published As

Publication number Publication date
JPS57125891A (en) 1982-08-05

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