JPS64638Y2 - - Google Patents

Info

Publication number
JPS64638Y2
JPS64638Y2 JP1980133532U JP13353280U JPS64638Y2 JP S64638 Y2 JPS64638 Y2 JP S64638Y2 JP 1980133532 U JP1980133532 U JP 1980133532U JP 13353280 U JP13353280 U JP 13353280U JP S64638 Y2 JPS64638 Y2 JP S64638Y2
Authority
JP
Japan
Prior art keywords
rack
storage
fuel
spent fuel
lattice
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
JP1980133532U
Other languages
Japanese (ja)
Other versions
JPS5761599U (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 JP1980133532U priority Critical patent/JPS64638Y2/ja
Publication of JPS5761599U publication Critical patent/JPS5761599U/ja
Application granted granted Critical
Publication of JPS64638Y2 publication Critical patent/JPS64638Y2/ja
Expired 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)

Description

【考案の詳細な説明】 この考案は原子炉施設における使用済燃料を水
を満たしたプール内に貯蔵する際の貯蔵ラツクに
関するものである。
[Detailed description of the invention] This invention relates to a storage rack for storing spent fuel in a water-filled pool in a nuclear reactor facility.

原子炉の炉心から取出された使用済燃料は高崩
壊熱を有するために、施設内で高崩壊熱が十分減
衰するまで水プール内に浸漬して冷却貯蔵され
る。この手段として頭記使用済燃料貯蔵ラツク
(以下単に「ラツク」と呼称する)が用いられる。
かかるラツクは多数の使用済燃料を並べて収容支
持するものであり、一般に構築物として耐震性の
高い十分な強度を有することに加えて、収容効率
の良いことが望まれる。
Since the spent fuel taken out from the core of a nuclear reactor has high decay heat, it is cooled and stored in a water pool within the facility until the high decay heat is sufficiently attenuated. As this means, the above-mentioned spent fuel storage rack (hereinafter simply referred to as "rack") is used.
Such racks are used to accommodate and support a large number of spent fuels, and are generally required to have sufficient strength as a structure with high earthquake resistance, as well as to have good storage efficiency.

ここで従来におけるラツクの構造を第1図およ
び第3図について述べる。図において1は箱形の
ラツクフレームであり、該ラツクフレーム1は四
隈および各周辺の中間に配置した垂直梁2、垂直
梁2の相互間を結合した上下複数段の水平梁3、
傾めの筋かいとなる補強梁4、ラツクを水プール
の底壁に固定するための支持板5、および強度を
高めるための中央垂直主柱6などを組合わせたラ
ーメン構造して組立てられている。更にラツクフ
レーム1には上下面に格子梁7を設け、この格子
梁7によつてラツクフレームの内方空間を格子状
に仕切り、多数の燃料収容室8を区画形成してい
る。なお格子梁7の一部は主柱6と水平梁3とを
結合する補強梁も兼ねている。使用済燃料は図示
されていない燃料取扱機によつて炉心より水プー
ルへ移送され、ラツク上方より指定番地の収容室
8へ吊り降ろされる。なお図示されていないが実
際のラツクには各収容室8ごとに燃料を案内支持
する部材が上下数箇所に設けてある。
Here, the structure of a conventional rack will be described with reference to FIGS. 1 and 3. In the figure, 1 is a box-shaped rack frame, and the rack frame 1 includes vertical beams 2 placed in the middle of the four corners and each periphery, horizontal beams 3 in multiple upper and lower stages connecting the vertical beams 2,
It is assembled into a rigid frame structure that combines reinforcing beams 4 that act as braces for tilting, support plates 5 for fixing the rack to the bottom wall of the water pool, and central vertical main pillars 6 to increase strength. There is. Further, the rack frame 1 is provided with lattice beams 7 on the upper and lower surfaces, and the lattice beams 7 partition the inner space of the rack frame into a lattice shape, thereby defining a large number of fuel storage chambers 8. Note that a part of the lattice beam 7 also serves as a reinforcing beam that connects the main column 6 and the horizontal beam 3. The spent fuel is transferred from the core to the water pool by a fuel handling machine (not shown), and is lowered from above the rack into the storage chamber 8 at a designated address. Although not shown in the drawings, in the actual rack, members for guiding and supporting the fuel are provided at several locations above and below for each storage chamber 8.

ところで格子梁7は第3図に示すようにラツク
フレーム1の外周枠の各辺と平行に配列設置さ
れ、かつ互に隣接する各収容室8の隣接相互間に
は符号9で示す使用済燃料の未臨界を保証するに
必要な離間距離を確保するよう未臨界ピツチPを
基準として各格子梁7の縦、横ピツチが設定され
ている。ここで図中の点線lは未臨界ピツチPを
基準にして格子状に並べた各使用済燃料の収容位
置を通る縦、横の配列仮想線である。なお第3図
には説明上第1図の垂直支柱6は省略してある。
By the way, the lattice beams 7 are arranged parallel to each side of the outer peripheral frame of the rack frame 1 as shown in FIG. The vertical and horizontal pitches of each lattice beam 7 are set with reference to the subcritical pitch P to ensure the necessary separation distance to guarantee subcriticality. Here, the dotted line l in the figure is a vertical and horizontal array virtual line passing through the storage positions of each spent fuel arranged in a grid with the subcritical pitch P as a reference. Note that the vertical support 6 shown in FIG. 1 is omitted from FIG. 3 for illustrative purposes.

ところで、上記従来構造のラツクには以下に述
べるような問題点がある。すなわち原子炉から取
出されるものには前述した使用済燃料の他に、各
種炉心廃棄物があり、これら炉心廃棄物は使用済
燃料と同様に施設外へ搬出する以前に一時的に施
設内、特に搬出ルートの途中にある水プール内の
ラツクに貯蔵することが一般に行われている。し
かして第3図からも明らかなように、従来のラツ
クでは未臨界ピツチPを基準に画いた燃料収容位
置の配列仮想線lに対して格子梁7が平行に配置
されていて、燃料収容室8以外にはまつたく炉心
廃棄物を専用に収容する余分なスペースが形成さ
れていない。このために炉心廃棄物をラツク内に
貯蔵するには止むを得ず燃料収容室8の一部を割
いて符号10で示す炉心廃棄物を貯蔵していた
が、この方法では使用済燃料の貯蔵容量が炉心廃
棄物を貯蔵した分だけ差し引かれて低下し、使用
済燃料の貯蔵に支障を来たすことになる。
By the way, the above-mentioned conventional structure has the following problems. In other words, in addition to the spent fuel mentioned above, there are various types of core waste that are removed from the reactor, and like spent fuel, these core wastes are temporarily stored inside the facility before being transported outside the facility. In particular, it is common practice to store them in racks in water pools along the route of transportation. However, as is clear from FIG. 3, in the conventional rack, the lattice beams 7 are arranged parallel to the imaginary line l of the fuel storage positions drawn with the subcritical pitch P as a reference, and the fuel storage No extra space was formed except for No. 8 to specifically accommodate core waste. For this reason, in order to store the core waste in a rack, it was unavoidable to open up a part of the fuel storage chamber 8 to store the core waste indicated by the reference numeral 10. However, in this method, the spent fuel The capacity will be reduced by the amount of core waste stored, which will impede the storage of spent fuel.

本考案は上述の点にかんがみなされたものであ
り、その目的はラツクを大形化することなしに、
しかも各燃料収容室の隣接相互間には所要の未臨
界ピツチを確保しつつ、必要な本数の使用済燃料
のほかに同時に炉心廃棄物も貯蔵できるようにし
た収容効率の高い新規な使用済燃料貯蔵ラツクを
提供することにある。
The present invention was made in consideration of the above points, and its purpose is to
Moreover, it is a new type of spent fuel with high storage efficiency that can store the required number of spent fuel and core waste at the same time while ensuring the required subcritical pitch between adjacent fuel storage chambers. The purpose is to provide storage racks.

かかる目的は本考案により、未臨界ピツチを基
準にしてラツクフレームの内方空間に格子状に並
べた各使用済燃料の収容位置を通る縦、横の配列
仮想線に対して、斜めに配列した格子梁をそな
え、前記格子梁により多数の燃料収容室をラツク
フレーム内に斜方向に区画形成し、その際燃料収
容室の相互の中間に炉心廃棄物収容室を形成した
ことにより達成される。
This purpose is achieved by the present invention, in which the spent fuel is arranged diagonally with respect to the vertical and horizontal imaginary lines passing through the storage positions of the spent fuel arranged in a lattice pattern in the inner space of the rack frame with the subcritical pitch as a reference. This is achieved by providing a lattice beam, which divides a large number of fuel storage chambers in a diagonal direction within the rack frame, and forming a core waste storage chamber between the fuel storage chambers.

以下本考案を図示実施例に基づき詳述する。 The present invention will be described in detail below based on illustrated embodiments.

第2図に本考案一実施例の外形斜視図、第4図
にその格子配列を表わす平面図を示す。この実施
例と第1図,第3図に示した従来のラツクと較べ
ての相違点は第4図で明示されているように、格
子梁7が未臨界ピツチPを基準にして第3図と同
様に画いた格子状に並ぶ各使用済燃料9の収容位
置を通る縦,横の配列仮想線lに対し、該仮想線
を斜めに横切るように配置されている。すなわち
各格子梁7は箱形ラツクフレーム1の対角線と平
行に延在する。この格子梁7の斜め配列により、
ラツクフレーム1の内方空間には未臨界ピツチP
を確保しつつ第3図と同じ数の燃料収容室8とと
もに、各収容室8の相互の間には炉心廃棄物10
の貯蔵スペースとして利用できる収容室11が区
画形成されることになる。なおかかる点第3図で
は、第4図における収容室11の位置する箇所を
丁度縦,横の格子梁が交叉して点有しているため
に炉心廃棄物10の専用収容室が形成できない。
したがつて従来と同じ外形寸法にもかかわらず必
要な本数の使用済燃料を未臨界ピツチを確保して
貯蔵させつつ、しかも炉心廃棄物を燃料収容室8
の一部を割くことなしに専用の収容室11に貯蔵
でき、その実益は極めて大である。
FIG. 2 shows an external perspective view of an embodiment of the present invention, and FIG. 4 shows a plan view showing its lattice arrangement. The difference between this embodiment and the conventional rack shown in FIGS. 1 and 3 is that, as clearly shown in FIG. They are arranged so as to diagonally cross the vertical and horizontal array imaginary lines 1 passing through the storage positions of the spent fuels 9 arranged in a grid pattern similarly drawn. That is, each lattice beam 7 extends parallel to the diagonal of the box-shaped rack frame 1. Due to this diagonal arrangement of the lattice beams 7,
There is a subcritical pitch P in the inner space of the rack frame 1.
While ensuring the same number of fuel storage chambers 8 as shown in FIG.
A storage chamber 11 that can be used as a storage space is divided into sections. Note that in FIG. 3, a dedicated storage chamber for the core waste 10 cannot be formed because the vertical and horizontal lattice beams intersect exactly at the location where the storage chamber 11 in FIG. 4 is located.
Therefore, despite the same external dimensions as before, the required number of spent fuel can be stored in a subcritical pit, and core waste can be stored in the fuel storage chamber 8.
It can be stored in the dedicated storage chamber 11 without using any part of the storage space, and the practical benefit is extremely large.

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

第1図および第2図はそれぞれ従来および本考
案一実施例による使用済燃料貯蔵ラツクの外形斜
視図、第3図および第4図はそれぞれ第1図およ
び第2図における使用済燃料等の貯蔵配列を示す
略示平面図である。 1……箱形のラツクフレーム、7……格子梁、
8……燃料収容室、9……使用済燃料、10……
炉心廃棄物、11……炉心廃棄物収容室。
1 and 2 are external perspective views of a conventional spent fuel storage rack and an embodiment of the present invention, respectively, and FIGS. 3 and 4 are storage racks for spent fuel, etc. in FIGS. 1 and 2, respectively. FIG. 3 is a schematic plan view showing the arrangement. 1... Box-shaped rack frame, 7... Lattice beam,
8...Fuel storage chamber, 9...Spent fuel, 10...
Core waste, 11...core waste storage chamber.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 箱形のラツクフレームに格子梁を配列してラツ
クフレームの内方空間を格子状に仕切り、隣接相
互間に使用済燃料の未臨界ピツチを確保する多数
の燃料収容室を区画形成した原子炉用使用済燃料
の貯蔵ラツクにおいて、未臨界ピツチを基準にし
てラツクフレームの内方空間に格子状に並べた各
使用済燃料の収容位置を通る縦、横の配列仮想線
に対し斜めに配列した格子梁をそなえ、前記格子
梁により多数の燃料収容室をラツクフレーム内に
斜方向に区画形成し、その際各燃料収容室の相互
の中間に炉心廃棄物収容室を形成したことを特徴
とする原子炉用使用済燃料の貯蔵ラツク。
For nuclear reactors, lattice beams are arranged in a box-shaped rack frame to partition the inner space of the rack frame into a lattice pattern, forming a number of fuel storage chambers between adjacent spaces to ensure subcritical pitches for spent fuel. In a spent fuel storage rack, grids are arranged diagonally with respect to vertical and horizontal imaginary lines that pass through the storage positions of each spent fuel arranged in a lattice pattern in the inner space of the rack frame with the subcritical pitch as a reference. The lattice beam is used to partition a large number of fuel storage chambers in a diagonal direction within the rack frame, and at this time, a core waste storage chamber is formed between each of the fuel storage chambers. Storage rack for spent fuel for furnaces.
JP1980133532U 1980-09-19 1980-09-19 Expired JPS64638Y2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1980133532U JPS64638Y2 (en) 1980-09-19 1980-09-19

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1980133532U JPS64638Y2 (en) 1980-09-19 1980-09-19

Publications (2)

Publication Number Publication Date
JPS5761599U JPS5761599U (en) 1982-04-12
JPS64638Y2 true JPS64638Y2 (en) 1989-01-09

Family

ID=29493756

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1980133532U Expired JPS64638Y2 (en) 1980-09-19 1980-09-19

Country Status (1)

Country Link
JP (1) JPS64638Y2 (en)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4063999A (en) * 1976-01-28 1977-12-20 Westinghouse Electric Corporation Nuclear fuel storage arrangement

Also Published As

Publication number Publication date
JPS5761599U (en) 1982-04-12

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