JPH0216319Y2 - - Google Patents

Info

Publication number
JPH0216319Y2
JPH0216319Y2 JP1983164687U JP16468783U JPH0216319Y2 JP H0216319 Y2 JPH0216319 Y2 JP H0216319Y2 JP 1983164687 U JP1983164687 U JP 1983164687U JP 16468783 U JP16468783 U JP 16468783U JP H0216319 Y2 JPH0216319 Y2 JP H0216319Y2
Authority
JP
Japan
Prior art keywords
support plate
rack support
rack
nuclear fuel
pit
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
JP1983164687U
Other languages
Japanese (ja)
Other versions
JPS6072595U (en
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 filed Critical
Priority to JP1983164687U priority Critical patent/JPS6072595U/en
Publication of JPS6072595U publication Critical patent/JPS6072595U/en
Application granted granted Critical
Publication of JPH0216319Y2 publication Critical patent/JPH0216319Y2/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

  • Warehouses Or Storage Devices (AREA)
  • Supports For Pipes And Cables (AREA)

Description

【考案の詳細な説明】 本考案は使用済核燃料の貯蔵設備に関する。[Detailed explanation of the idea] The present invention relates to spent nuclear fuel storage equipment.

原子力発電プラントの定期検査の際、原子炉か
ら取り出された使用済核燃料の集合体は、原子炉
格納容器に隣接して設けられたピツト内に設置さ
れたラツクセルの中に、一旦保管され、ピツト内
の水によつて一定期間冷却された後、再処理工場
に運び出される。
During periodic inspections of nuclear power plants, spent nuclear fuel assemblies removed from the reactor are temporarily stored in a lux cell installed in a pit adjacent to the reactor containment vessel, and then removed from the pit. After being cooled by the water inside for a certain period of time, it is transported to a reprocessing plant.

従来の使用済核燃料の貯蔵設備の一例が第1図
に示され、ラツクセル01は上下2段のラツク支
持板02によつて支持され、このラツク支持板0
2はピツトの壁04に取り付けられた埋込板05
に溶接09で取付けて固定されていた。03は埋
込板05をピツトの壁04に支持固定するための
埋込金物、08はラツク支持板02を支持する為
の支柱を示す。
An example of a conventional spent nuclear fuel storage facility is shown in FIG.
2 is an embedded board 05 attached to the wall 04 of the pit
It was attached and fixed with welding 09. Reference numeral 03 indicates an embedded metal fitting for supporting and fixing the embedded plate 05 to the wall 04 of the pit, and 08 indicates a column for supporting the rack support plate 02.

原子炉から取出された使用済核燃料は、幾分余
熱を持つているので、この使用済核燃料をラツク
セル01内に収納すると、ラツクセル01及びラ
ツク支持板02は使用済核燃料によつて加熱され
て熱膨張しようとするが、埋込板05がピツトの
壁04に埋込金物03を介して固定されているの
で、ラツク支持板02と埋込板05とはその熱膨
張差により熱応力を受け、従つて、ラツク支持板
02と埋込板05の強度を増強せざるを得なかつ
た。
The spent nuclear fuel taken out from the reactor has some residual heat, so when this spent nuclear fuel is stored in the rack cell 01, the rack cell 01 and the rack support plate 02 are heated by the spent nuclear fuel and emit heat. However, since the embedded plate 05 is fixed to the wall 04 of the pit via the embedded metal fittings 03, the rack support plate 02 and the embedded plate 05 are subjected to thermal stress due to the difference in thermal expansion. Therefore, it was necessary to increase the strength of the rack support plate 02 and the embedded plate 05.

本考案は上記問題に対処するために提案された
ものであつて、その要旨とするところは、冷却水
を貯溜するピツトと、同ピツト内に垂直に配置さ
れ使用済核燃料を収容する複数個の筒状ラツクセ
ルと、同ラツクセルを連結支持する略水平に配置
された上下2段のラツク支持板とを具えた使用済
核燃料の貯蔵設備において、前記ラツク支持板の
周辺に設けられて冷却水の流動を許容する切欠部
と、前記ラツク支持板の外周にピツト壁と平行に
形成され且つ同ラツク支持板により両端を固定さ
れた滑り部材と、ピツト壁に固定され前記滑り部
材を上下方向および水平方向に移動可能に囲んで
支持する相対変位吸収継手とを具えたことを特徴
とする使用済核燃料の貯蔵設備にある。
The present invention was proposed to address the above problem, and its gist is that it includes a pit for storing cooling water, and a plurality of pits arranged vertically within the pit for storing spent nuclear fuel. In a spent nuclear fuel storage facility equipped with a cylindrical rack cell and two rack support plates arranged approximately horizontally, one above the other, which connect and support the rack cell, the rack support plate is provided around the rack support plate to control the flow of cooling water. a sliding member formed on the outer periphery of the rack support plate parallel to the pit wall and fixed at both ends by the rack support plate; and a sliding member fixed to the pit wall that allows the sliding member to move vertically and horizontally. and a relative displacement absorbing joint that movably surrounds and supports the spent nuclear fuel.

本考案においては上記構成を具えているので、
原子炉より取り出した使用済核燃料をラツクセル
内に収納したときこれによつてラツク支持板が加
熱されて熱膨張しても、このラツク支持板はピツ
ト壁に相対変位吸収継手を介して取り付けられて
いるため、ラツク支持板はピツト壁に対し相対変
位することができる。従つて、従来のようにラツ
ク支持板に熱応力が作用することはないので、ラ
ツク支持板が破損するおそれはなく、その強度を
低減できるから安価に製造することができる。
Since the present invention has the above configuration,
Even if the rack support plate is heated and thermally expanded when spent nuclear fuel taken out from the reactor is stored in the rack cell, the rack support plate is attached to the pit wall via a relative displacement absorbing joint. Because of this, the rack support plate can be displaced relative to the pit wall. Therefore, unlike the conventional case, thermal stress is not applied to the rack support plate, so there is no risk of the rack support plate being damaged, and its strength can be reduced, so it can be manufactured at low cost.

以下、本考案を第2図ないし第4図に示す1実
施例を参照しながら具体的に説明する。
Hereinafter, the present invention will be explained in detail with reference to an embodiment shown in FIGS. 2 to 4.

第2図は部分的平面図、第3図は第2図の−
線に沿う断面図、第4図は相対変位吸収継手を
示す斜視図である。
Figure 2 is a partial plan view, Figure 3 is the -
FIG. 4 is a perspective view showing the relative displacement absorbing joint.

第2図ないし第4図において、1は使用済核燃
料を受容れるラツクセル、2はラツクセル1を支
持するラツク支持板で、図示されていないが、従
来のラツク支持板と同様、複数の支柱に固定され
て冷却水が貯溜されたピツト内に上下2段に水平
に配設されている。5は埋込板でピツト壁4内に
埋込まれた埋込金物3を介してピツト壁4に取り
付けられている。ラツク支持板2のピツト壁4の
近くを四角形に切り取ることによつてその切欠部
8と縁との間に形成されたピツト壁4に沿つて平
行に延びる桟橋部2aに断面コの字状のホルダー
6を嵌め、その開放端にホルダーアダプタ6aを
溶接してさや状にして桟橋部2aを掴む。ホルダ
ー6の上面に固定金具7を溶接し、この固定金具
7を埋込板5に溶接して固定する。寸法aは、ラ
ツク支持板2の縁に沿つた水平方向の熱膨張吸収
代を、寸法bは上下方向の熱膨張吸収代を示す。
かくして、ラツク支持板2は、桟橋部2a、ホル
ダー6、ホルダーアダプター6a、固定金具7か
らなる相対変位吸収継手10及び埋込板5、埋込
金物3を介してピツト壁4に取り付けられる。
In Figures 2 to 4, 1 is a rack cell that can receive spent nuclear fuel, and 2 is a rack support plate that supports the rack cell 1. Although not shown, the rack support plate is fixed to a plurality of supports like a conventional rack support plate. They are arranged horizontally in two stages, upper and lower, in a pit in which cooling water is stored. Reference numeral 5 denotes an embedded plate which is attached to the pit wall 4 via an embedded metal fitting 3 embedded in the pit wall 4. By cutting the rack support plate 2 near the pit wall 4 into a rectangular shape, a U-shaped cross section is formed on the pier portion 2a extending parallel to the pit wall 4, which is formed between the notch 8 and the edge. The holder 6 is fitted, and a holder adapter 6a is welded to the open end of the holder to form a sheath shape to grip the pier portion 2a. A fixing metal fitting 7 is welded to the upper surface of the holder 6, and this fixing metal fitting 7 is welded and fixed to the embedded plate 5. The dimension a indicates the horizontal thermal expansion absorption along the edge of the rack support plate 2, and the dimension b indicates the vertical thermal expansion absorption.
Thus, the rack support plate 2 is attached to the pit wall 4 via the relative displacement absorbing joint 10 consisting of the pier portion 2a, the holder 6, the holder adapter 6a, the fixing fittings 7, the embedded plate 5, and the embedded metal fittings 3.

第5図は4分割されたラツク支持板2を具えた
使用済核燃料の貯蔵設備に本考案を適用した1例
を示す平面図で、隣接するラツク支持板2相互間
の隙間cはラツク支持板2の熱膨張吸収代として
充分な寸法とする必要がある。
FIG. 5 is a plan view showing an example in which the present invention is applied to a spent nuclear fuel storage facility equipped with a rack support plate 2 divided into four parts. It is necessary to have a size sufficient to absorb thermal expansion in step 2.

第6図は第5図における分割されたラツク支持
板2の1個を拡大して示し、図に示されるように
このラツク支持板2は隣接する各辺A,Bにそれ
ぞれ複数個の相対変位吸収継手10を具え、ラツ
ク支持板2のP矢方向の熱伸びは辺Bに取り付け
られた相対変位吸収継手10で吸収し、ラツク支
持板2のQ矢方向の熱伸びは辺Aに取り付けられ
た相対変位吸収継手10で吸収する。また、地震
発生時においても、P矢方向の揺動は辺Bに取り
付けられた相対変位吸収継手10が吸収し、Q矢
方向の揺動は辺Aに取り付けられた相対変位吸収
継手10が吸収する。
FIG. 6 shows an enlarged view of one of the divided rack support plates 2 in FIG. It is equipped with an absorption joint 10, and the thermal elongation of the rack support plate 2 in the P arrow direction is absorbed by the relative displacement absorption joint 10 attached to the side B, and the thermal elongation of the rack support plate 2 in the Q arrow direction is absorbed by the relative displacement absorption joint 10 attached to the side A. The relative displacement is absorbed by the relative displacement absorbing joint 10. Furthermore, even in the event of an earthquake, the relative displacement absorption joint 10 attached to side B absorbs the shaking in the P arrow direction, and the relative displacement absorption joint 10 attached to side A absorbs the shaking in the Q arrow direction. do.

第7図は大容量の使用済核燃料の貯蔵設備に本
考案を適用した1例を示す平面図で、ラツク支持
板2はその工作、運搬上の便宜のためその大きさ
に限界があるので、これは8個のラツク支持板2
を具えている。隣接するラツク支持板2を継ぎ金
物11を用いて相互に連結し或は直接溶接するこ
とによつて連結し4個のラツク支持板とすること
ができる。
FIG. 7 is a plan view showing an example in which the present invention is applied to a large-capacity spent nuclear fuel storage facility.The rack support plate 2 has a limited size due to convenience in construction and transportation. This is 8 rack support plates 2
It is equipped with Adjacent rack support plates 2 can be connected to each other using joints 11 or by direct welding to form four rack support plates.

第8図は相対変位吸収継手の他の例を示す斜視
図で、ラツク支持板2の縁と平行に、縁から所定
間隔を隔てるように滑り棒12をラツク支持板2
と渡し棒14を介して連結し、この滑り棒13を
ホルダー6内に嵌合したものである。この滑り棒
12は平鋼に限らず、角棒、丸パイプ等を用いる
ことができ、また、渡し棒も、平鋼に限らず、山
型鋼、角棒、丸パイプその他の鋼材を用いること
ができる。
FIG. 8 is a perspective view showing another example of a relative displacement absorbing joint, in which the sliding rod 12 is inserted parallel to the edge of the rack support plate 2 at a predetermined distance from the edge.
This sliding rod 13 is fitted into the holder 6. The sliding rod 12 is not limited to flat steel, but can also be a square bar, round pipe, etc., and the passing rod is not limited to flat steel, but can also be made of angle-shaped steel, square bar, round pipe, or other steel materials. can.

かくして、原子炉から取り出した使用済核燃料
をラツクセル1に収納した場合、ラツクセル1及
びラツク支持板2が熱膨張したとき、ラツク支持
板2の水平方向の熱伸びは相対変位吸収継手10
の水平方向の熱膨張吸収代aで吸収し、上下方向
の熱伸びは相対変位吸収継手10の上下方向の熱
膨張吸収代bで吸収できる。なお、ラツクセル1
をラツク支持板2に溶接することなくラツク支持
板2に穿設した穴に挿入した場合でも支柱の熱伸
び量だけはラツク支持板2が持ち上げられるの
で、この場合は支柱の熱伸び量に相当する上下方
向の熱膨張吸収代を存置する必要がある。
Thus, when spent nuclear fuel taken out from a nuclear reactor is stored in rack cell 1, when rack cell 1 and rack support plate 2 thermally expand, the horizontal thermal expansion of rack support plate 2 is equal to the relative displacement absorbing joint 10.
It can be absorbed by the horizontal thermal expansion absorption allowance a, and the vertical thermal expansion can be absorbed by the vertical thermal expansion absorption allowance b of the relative displacement absorbing joint 10. In addition, Luxel 1
Even if the rack support plate 2 is inserted into the hole drilled in the rack support plate 2 without welding it to the rack support plate 2, the rack support plate 2 will be lifted by the amount of thermal expansion of the support column, so in this case, it corresponds to the amount of thermal expansion of the support column. It is necessary to provide an allowance for thermal expansion absorption in the vertical direction.

以上のように、ラツク支持板の水平方向及び上
下方向の変位は相対変位吸収継手10で吸収でき
るので、従来のようにラツク支持板及び埋込板に
応力が作用することはなく、従つて、これらの強
度を低減できるので、安価に製造できる。
As mentioned above, since the horizontal and vertical displacements of the rack support plate can be absorbed by the relative displacement absorbing joint 10, stress does not act on the rack support plate and the embedded plate as in the conventional case. Since these strengths can be reduced, manufacturing can be done at low cost.

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

第1図は従来の使用済核燃料の貯蔵設備の1例
を部分的に破断して示す斜視図、第2図ないし第
4図は本考案の1実施例を示し、第2図は部分的
平面図、第3図は第2図の−線に沿う断面
図、第4図は相対変位吸収継手を示す斜視図、第
5図は4分割されたラツク支持板を具えた使用済
核燃料の貯蔵設備に本考案を適用した例を示す平
面図、第6図は第5図における分割されたラツク
支持板の1個を拡大して示す平面図、第7図は大
容量の使用済核燃料の貯蔵設備に本考案を適用し
た例を示す平面図、第8図は相対変位吸収継手の
他の例を示す斜視図である。 ラツクセル……1、ラツク支持板……2、ピツ
ト壁……4、支柱……8、相対変位吸収継手……
10。
Fig. 1 is a partially cutaway perspective view of an example of a conventional spent nuclear fuel storage facility, Figs. 2 to 4 show an embodiment of the present invention, and Fig. 2 is a partial plan view. Figure 3 is a sectional view taken along the - line in Figure 2, Figure 4 is a perspective view showing a relative displacement absorption joint, and Figure 5 is a spent nuclear fuel storage facility equipped with a rack support plate divided into four parts. FIG. 6 is a plan view showing an enlarged view of one of the divided rack support plates in FIG. 5, and FIG. 7 is a large-capacity spent nuclear fuel storage facility. FIG. 8 is a plan view showing an example to which the present invention is applied, and FIG. 8 is a perspective view showing another example of the relative displacement absorbing joint. Rack cell...1, Rack support plate...2, Pit wall...4, Support column...8, Relative displacement absorption joint...
10.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 冷却水を貯溜するピツトと、同ピツト内に垂直
に配置され使用済核燃料を収容する複数個の筒状
ラツクセルと、同ラツクセルを連結支持する略水
平に配置された上下2段のラツク支持板とを具え
た使用済核燃料の貯蔵設備において、前記ラツク
支持板の周辺に設けられて冷却水の流動を許容す
る切欠部と、前記ラツク支持板の外周にピツト壁
と平行に形成され且つ同ラツク支持板により両端
を固定された滑り部材と、ピツト壁に固定され前
記滑り部材を上下方向および水平方向に移動可能
に囲んで支持する相対変位吸収継手とを具えたこ
とを特徴とする使用済核燃料の貯蔵設備。
A pit for storing cooling water, a plurality of cylindrical rack cells arranged vertically in the pit for storing spent nuclear fuel, and two rack support plates arranged approximately horizontally, upper and lower, that connect and support the rack cells. A spent nuclear fuel storage facility comprising: a notch provided around the rack support plate to allow the flow of cooling water; and a notch formed on the outer periphery of the rack support plate parallel to the pit wall A spent nuclear fuel system comprising a sliding member fixed at both ends by plates, and a relative displacement absorbing joint fixed to a pit wall and surrounding and supporting the sliding member so as to be movable in the vertical and horizontal directions. Storage equipment.
JP1983164687U 1983-10-26 1983-10-26 Spent nuclear fuel storage facility Granted JPS6072595U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1983164687U JPS6072595U (en) 1983-10-26 1983-10-26 Spent nuclear fuel storage facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1983164687U JPS6072595U (en) 1983-10-26 1983-10-26 Spent nuclear fuel storage facility

Publications (2)

Publication Number Publication Date
JPS6072595U JPS6072595U (en) 1985-05-22
JPH0216319Y2 true JPH0216319Y2 (en) 1990-05-02

Family

ID=30361000

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1983164687U Granted JPS6072595U (en) 1983-10-26 1983-10-26 Spent nuclear fuel storage facility

Country Status (1)

Country Link
JP (1) JPS6072595U (en)

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5535298A (en) * 1978-08-30 1980-03-12 Kraftwerk Union Ag Storage of spent fuel of bwr type reactor
JPS5566797A (en) * 1978-11-06 1980-05-20 Combustion Eng Fuel storage rack
JPS5725797A (en) * 1980-07-24 1982-02-10 Nippon Telegr & Teleph Corp <Ntt> Piezoelectric electroacoustic transducer

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58103398U (en) * 1982-01-06 1983-07-14 三菱重工業株式会社 Nuclear fuel assembly storage pool

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5535298A (en) * 1978-08-30 1980-03-12 Kraftwerk Union Ag Storage of spent fuel of bwr type reactor
JPS5566797A (en) * 1978-11-06 1980-05-20 Combustion Eng Fuel storage rack
JPS5725797A (en) * 1980-07-24 1982-02-10 Nippon Telegr & Teleph Corp <Ntt> Piezoelectric electroacoustic transducer

Also Published As

Publication number Publication date
JPS6072595U (en) 1985-05-22

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