JPH028279B2 - - Google Patents
Info
- Publication number
- JPH028279B2 JPH028279B2 JP57203865A JP20386582A JPH028279B2 JP H028279 B2 JPH028279 B2 JP H028279B2 JP 57203865 A JP57203865 A JP 57203865A JP 20386582 A JP20386582 A JP 20386582A JP H028279 B2 JPH028279 B2 JP H028279B2
- Authority
- JP
- Japan
- Prior art keywords
- storage rack
- lid
- water
- fuel assembly
- nuclear fuel
- 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 - Lifetime
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
(産業上の利用分野)
本発明は、原子燃料集合体、特に定期検査時、
原子燃料集合体から漏出する核分裂生成物の漏洩
検査に使用する検査装置に関するものである。DETAILED DESCRIPTION OF THE INVENTION (Industrial Field of Application) The present invention is directed to nuclear fuel assemblies, particularly during periodic inspections.
This invention relates to an inspection device used for leak inspection of nuclear fission products leaking from a nuclear fuel assembly.
(従来の技術)
原子燃料集合体は、その性状により原子炉内で
燃焼後、その健全性を検査し再度使用可能かどう
か確認するために定期検査に供され、使用した原
子燃料集合体の被覆管のピンホールなどの検査の
ために炉停止後、炉心から引き出して漏洩検査が
行われている。(Prior art) Due to its properties, nuclear fuel assemblies are subjected to periodic inspections after combustion in a nuclear reactor to inspect their integrity and confirm whether they can be used again. After the reactor is shut down to inspect for pinholes in the tubes, they are pulled out of the core and inspected for leaks.
ところで、定期検査時の漏洩検査では、従来原
子炉から原子燃料集合体を燃料取換クレーンにて
取り出し、該原子燃料集合体を別途、離れた位置
にあるプールに運般して各検査に供されるまで当
該プール内にて保管ラツク内に収納保管する。そ
して、この収納された燃料集合体を次にシツピン
グキヤン内に入れ蓋止め密封し、ここで燃料集合
体を断熱条件下におくことで昇温させ、これによ
り燃料棒の被覆管内部を昇圧させて同被覆管に存
在するピンホール等から核分裂生成物を漏出さ
せ、水又はガスに溶出した核分裂生成物の存否を
上記水、ガスを分析することによつて決定してい
た。 By the way, in leakage inspections during periodic inspections, conventionally the nuclear fuel assemblies are taken out of the reactor using a fuel exchange crane, and the nuclear fuel assemblies are separately transported to a separate pool for each inspection. Stored in a storage rack within the pool until the storage is completed. This stored fuel assembly is then placed in a shipping can and sealed with a lid, where the fuel assembly is placed under adiabatic conditions to raise its temperature, which increases the pressure inside the fuel rod cladding tube. Fission products were allowed to leak through pinholes, etc. present in the cladding tube, and the presence or absence of fission products eluted into water or gas was determined by analyzing the water or gas.
しかしながら、この従来方法では原子燃料集合
体を原子炉から取り出しプールに運搬した後にお
いて、更に保管ラツクと漏洩燃料検査装置との間
を搬送する必要があり、作業時間の不経済はもと
より、作業性において問題があつた。 However, in this conventional method, after the nuclear fuel assembly is taken out of the reactor and transported to the pool, it is necessary to transport it between the storage rack and the leakage fuel inspection equipment, which not only wastes working time but also reduces work efficiency. There was a problem.
そこで、近時、この改善を目指し、特に保管ラ
ツクより漏洩燃料検査装置への移動を省略し、作
業時間の短縮と、作業性改善を図ることを目的と
して使用した燃料集合体を遮蔽された保管ラツク
に収納し、ここで該燃料集合体を断熱条件下にお
くことで昇温させ、これにより燃料棒被覆管内部
を昇温させて同被覆管のピンホールなどから該分
裂生成物を水中へ漏出させ、該水を採集して核分
裂生成物を検知する方法ならびにそのための閉鎖
可能な蓋付き保管ラツク、保管ラツク内の水採集
機構、原子燃料集合体の吊下移送機構からなる検
査装置が提案されている。(特開昭58−182593号
公報参照)
(発明が解決しようとする課題)
しかしながら、上記提案になる検査装置は保管
ラツクの上下からしか水の侵入が得られず、従つ
て、燃料保管時、その分だけ燃料の温度上昇が大
きくなるという問題が残されている。 Therefore, in recent years, we have been aiming to improve this, particularly by omitting the transfer of fuel assemblies from storage racks to leakage testing equipment, shortening work time, and improving workability by shielding fuel assemblies. Here, the fuel assembly is placed under adiabatic conditions to raise its temperature, which raises the temperature inside the fuel rod cladding tube and releases the fission products into the water through pinholes in the cladding tube. A method for detecting fission products by leaking water and collecting the water is proposed, as well as an inspection device for this purpose consisting of a storage rack with a closable lid, a water collection mechanism in the storage rack, and a suspension transfer mechanism for nuclear fuel assemblies. has been done. (Refer to Japanese Unexamined Patent Publication No. 58-182593.) (Problems to be Solved by the Invention) However, the inspection device proposed above allows water to enter only from the top and bottom of the storage rack. The problem remains that the temperature rise of the fuel increases accordingly.
本発明は上述の問題に鑑み、更にその問題解消
を図ることを目途として保管ラツクの構成に改善
を加え、燃料保管時における保管ラツク内の温度
上昇を小さくし、燃料保管状態を良好とすると共
に、蓋止検査時は水の侵入を下方のみに止めて崩
壊熱により燃料集合体の昇温を扶けることを目的
とするものである。 In view of the above-mentioned problems, and with the aim of further solving the problems, the present invention improves the structure of the storage rack, reduces the temperature rise inside the storage rack during fuel storage, and improves the fuel storage condition. During the lid closure inspection, the purpose is to prevent water from entering only in the downward direction and to prevent the temperature of the fuel assembly from increasing due to decay heat.
(課題を解決するための手段)
即ち、上記目的を達成するため本発明は、周壁
によつて囲繞形成され、上部開口を開閉する蓋を
備えて内部に原子燃料集合体を収納保管する保管
ラツクと、該保管ラツクの蓋に取り付けられ、上
方へ延びるホースならびにポンプ手段を有して保
管ラツク内の水を採集する水採集機構と、前記保
管ラツクの上部開口を通じて原子燃料集合体を該
保管ラツク内へ移動挿入する原子燃料集合体の吊
下移動機構を具備し構成してなる漏洩検査装置に
おいて、更に保管ラツクの周壁面を少なくともそ
の一部においてその上部開口を蓋止めすることに
よつて閉鎖される開閉可能な遮蔽板により形成せ
しめて構成している。(Means for Solving the Problems) That is, in order to achieve the above object, the present invention provides a storage rack that is surrounded by a peripheral wall, has a lid for opening and closing an upper opening, and stores and stores nuclear fuel assemblies therein. a water collection mechanism attached to the lid of the storage rack and having an upwardly extending hose and pump means to collect water in the storage rack; and a water collection mechanism for collecting water in the storage rack through an upper opening of the storage rack. In the leakage inspection device comprising a suspension movement mechanism for a nuclear fuel assembly to be moved and inserted into the storage rack, the storage rack is further closed by covering at least a portion of the peripheral wall surface of the storage rack. It is constructed by a shielding plate that can be opened and closed.
(作用)
次に上記構成を有する漏洩検査装置による検査
状況について説明すると、一般に原子炉より取り
出された使用済みの原子燃料集合体の定期検査に
際して、通常、原子燃料集合体は、先ず、燃料取
換クレーンを用いて原子炉炉心より個々に引き出
される。そして、該場所より離れた位置にあるプ
ール内に置かれている保管ラツク内に収納され
る。(Function) Next, to explain the inspection status using the leakage inspection device having the above configuration, during periodic inspection of a used nuclear fuel assembly taken out from a nuclear reactor, the nuclear fuel assembly is usually first inspected for fuel removal. They are pulled out individually from the reactor core using a replacement crane. Then, it is stored in a storage rack placed in a pool located at a distance from the location.
そこで、従来方式では、更にその原子燃料集合
体をチユーブに入れ、漏洩検査装置の位置まで運
搬するのを必要としていたが、本発明は運搬する
ことなく、保管ラツク内を閉ざされた空間とする
ことにより、この空間内断熱条件下で前記原子燃
料集合体の放射性核分裂生成物の崩壊作用によつ
て崩壊熱を発生し、該集合体内の温度を昇温さ
せ、これにより該集合体の燃料を被覆している燃
料被覆管内部が昇圧し、該管にピンホールなどの
外傷が存在すると、ここから核分裂生成物が前記
保管ラツクと原子燃料集合体との間の水中に漏洩
する。そして、前記の漏出した核分裂生成物中水
溶性の生成物は前記水中に溶出し、該水を採集し
水分析器により核分裂生成物の存否を確認して、
前記原子燃料集合体の燃料被覆管の健全性を検査
する。 Therefore, in the conventional method, it was necessary to further put the nuclear fuel assembly into a tube and transport it to the location of the leakage inspection device, but the present invention does not require transport and makes the inside of the storage rack a closed space. As a result, decay heat is generated by the decay effect of the radioactive fission products of the nuclear fuel assembly under the adiabatic conditions in the space, raising the temperature inside the assembly, thereby increasing the fuel of the assembly. If the pressure inside the fuel cladding tube increases and there is a pinhole or other damage in the tube, fission products will leak from there into the water between the storage rack and the nuclear fuel assembly. Then, water-soluble products in the leaked fission products are eluted into the water, and the water is collected and the presence or absence of fission products is confirmed using a water analyzer.
The integrity of the fuel cladding of the nuclear fuel assembly is inspected.
このとき、上記構成では周壁の遮蔽板が開状態
では上下及び横方向から水の侵入が起こり、それ
だけ燃料の温度上昇が小さくなり、良好な燃料保
管状態を得ることができ、一方、遮蔽板を閉じ、
蓋をした状態では水の侵入は下方のみで極めて小
さく、崩壊熱により燃料集合体の昇温を扶ける有
利さを具える。 At this time, in the above configuration, when the shielding plate of the peripheral wall is open, water will enter from above and below and from the sides, and the temperature rise of the fuel will be correspondingly smaller, making it possible to obtain a good fuel storage condition. close,
When the lid is closed, water intrusion is extremely small only in the downward direction, which has the advantage of supporting the temperature rise of the fuel assembly by decay heat.
(実施例)
以下、更に添付図面を参照し、上記本発明装置
の実施例を説明する。(Embodiments) Hereinafter, embodiments of the apparatus of the present invention will be described with further reference to the accompanying drawings.
第1図及び第2図は本発明装置の全体の概要を
示し、図において、1は原子炉炉心から取り出さ
れた使用した原子燃料集合体、2は同燃料集合体
1を運搬移動させるための取扱工具、3は取扱工
具2のワイヤーを巻き取るためのホイストであつ
た、取扱工具2はその下端に燃料集合体保持機構
2aを有し、燃料集合体をその下端に吊下保持し
て下方の保管ラツク4内外へ上下動させ、原子燃
料集合体の吊下移動機構Aを構成している。 FIGS. 1 and 2 show an overview of the entire apparatus of the present invention. In the figures, 1 is a used nuclear fuel assembly taken out from the reactor core, and 2 is a part for transporting the fuel assembly 1. The handling tool 3 is a hoist for winding up the wire of the handling tool 2. The handling tool 2 has a fuel assembly holding mechanism 2a at its lower end, and holds the fuel assembly suspended from the lower end. The nuclear fuel assembly is moved up and down into and out of the storage rack 4, thereby forming a suspension movement mechanism A for the nuclear fuel assembly.
一方、4は保管ラツクであり、この保管ラツク
4は本発明において要部をなし、その詳細は第7
図に図示されているが、同図示例では簡単化のた
めにその内部を所要の閉ざされた空間となすのに
好適なようにその周壁面は四面共、閉鎖壁面によ
つて構成され、上部に開口41を有して、これに
開閉自在な蓋9が備えつけられている。 On the other hand, 4 is a storage rack, and this storage rack 4 constitutes a main part in the present invention, the details of which are described in the seventh section.
As shown in the figure, for the sake of simplicity, all four surrounding walls are composed of closed walls, and the upper It has an opening 41, and a lid 9 that can be opened and closed is attached to the opening 41.
この場合、蓋9は保管ラツク4と別個に離され
たものであつても、又、保管ラツク4に一部が連
結し回動させることによつて上部開口41を閉鎖
せしめるものであつてもよい。 In this case, the lid 9 may be separate from the storage rack 4, or may be partially connected to the storage rack 4 and rotated to close the upper opening 41. good.
そして、何れにあつても、蓋9閉めに便利なよ
うに保管ラツク4には上部開口41の下部位置に
蓋載せ台42が設けられていて、後述の水採集
時、適宜、ホイスト3などの機構によつて蓋載せ
台42上に載せ得るようになつている。 In any case, the storage rack 4 is provided with a lid mounting stand 42 at the lower part of the upper opening 41 so as to conveniently close the lid 9. A mechanism allows it to be placed on a lid holder 42.
なお、保管ラツク4は、第3図ハ,ニに示され
るように底部8に原子燃料集合体を支持し、か
つ、下方より保管ラツク4内へ内部の集合体崩壊
熱を除去するための水の侵入を自由ならしめるべ
く上下貫通可能な構造が採り入れられており、全
体としてプール(図示せず)内において組まれた
保管ラツク固定用の枠43内に挿入されて保持さ
れている。 The storage rack 4 supports the nuclear fuel assemblies at the bottom 8 as shown in FIG. In order to allow free entry, a vertically penetrable structure is adopted, and the whole is inserted and held within a frame 43 for fixing a storage rack assembled within a pool (not shown).
次に、一方、第1図のBは水採集機構を示し、
陸上などに配置されたポリビン7と、該ポリビン
7へ保管ラツク4内の水を吸い上げ採集するため
のホース5ならびにポンプからなつており、ホー
ス5の下方端は前記保管ラツク4の上部開口41
を閉鎖する蓋9に取り付けられ、蓋9によつて保
管ラツク4の上部開口41を閉鎖するとき、同時
に水採集機構Bが保管ラツク4に取り付けられ
る。 Next, on the other hand, B in Fig. 1 shows the water collection mechanism;
It consists of a plastic bin 7 placed on land or the like, a hose 5 and a pump for sucking up and collecting water in the storage rack 4 into the plastic bin 7, and the lower end of the hose 5 is connected to the upper opening 41 of the storage rack 4.
When the upper opening 41 of the storage rack 4 is closed by the lid 9, the water collection mechanism B is attached to the storage rack 4 at the same time.
しかして、叙上の原子燃料集合体1あるいは更
に蓋9を開閉するための吊下移動機構Aと、保管
ラツクA及び前記水採集機構Bによつて本発明に
おける漏洩検査装置の基本部分が構成されてお
り、この検査装置は、保管時においては、原子炉
炉心より取り出した既使用の原子燃料集合体1を
先ず、取扱工具2、ホイスト3で保管ラツク4の
位置まで移動させ、挿入する。勿論、このとき保
管ラツク4の底面は上下貫通状態で水の侵入は自
由である。 Therefore, the basic part of the leakage testing device of the present invention is constituted by the suspension moving mechanism A for opening and closing the nuclear fuel assembly 1 or the lid 9, the storage rack A, and the water collection mechanism B. During storage, this inspection device first moves a used nuclear fuel assembly 1 taken out from a nuclear reactor core to a storage rack 4 using a handling tool 2 and a hoist 3, and inserts it into the storage rack. Of course, at this time, the bottom surface of the storage rack 4 is in a vertically penetrating state, allowing water to freely enter.
そして、上記構成において、本発明装置は特に
その特徴として、保管ラツク4の構造に第5図な
いし第7図に示すような構造、即ち、保管ラツク
4の周壁面を開閉自在の遮蔽板10によつて構成
した構造が採り入れられている。 In the above configuration, the device of the present invention is particularly characterized in that the structure of the storage rack 4 is as shown in FIGS. A structure constructed in this way has been adopted.
図中、吊下移動機構A、水採集機構Bは前述し
た如き構造からなり、同一部分は同一符号で示
す。 In the figure, the suspension moving mechanism A and the water collection mechanism B have the structures described above, and the same parts are indicated by the same reference numerals.
以下、上記構造について第7図及び第8図を参
照しつつ詳述すると、図示の如く対向する両側板
11,12と、該両側板11,12間に亘設さ
れ、両側板11,12に形成された上下方向細長
ガイド溝13内に、夫々下部にばね14を有して
上下動可能に嵌着されている駆動棒15にピン1
6によつて連着されると共に両側板11,12に
対し支点軸17を支着せしめて駆動棒15の上下
動により支点軸17を支点として回動する遮蔽板
10とによつて構成されており、駆動棒15上部
の側板部分には切欠部18が設けられ、蓋9、下
部に下方へ向けて突出した突起部19が蓋止時、
挿入され、駆動棒15の上端を押圧するようにな
つている。 Hereinafter, the above structure will be described in detail with reference to FIGS. 7 and 8.As shown in the figure, the two side plates 11 and 12 are opposite each other, and the structure is provided between the two side plates 11 and 12. A pin 1 is attached to a drive rod 15 that is fitted into a vertically elongated guide groove 13, each having a spring 14 at the bottom thereof, so as to be movable up and down.
6, and a shielding plate 10 that supports a fulcrum shaft 17 on both side plates 11 and 12 and rotates about the fulcrum shaft 17 as a driving rod 15 moves up and down. A notch 18 is provided in the side plate portion of the upper part of the drive rod 15, and a protrusion 19 protrudes downward at the bottom of the lid 9 when the lid is closed.
It is inserted so as to press the upper end of the drive rod 15.
従つて、蓋9を保管ラツク4′上に載せたとき、
蓋9′の重さに対応して下部のばね14が圧縮さ
れ、駆動棒15の下方への移動を許して遮蔽板1
0を、その支点軸17を支点として回動させ、両
側板間を遮蔽する。一方、蓋9による荷重を除く
と、ばね14の付勢力により駆動棒15は上動
し、前記とは逆に支点軸17を支点として遮蔽板
を開放側へ回動させる。 Therefore, when the lid 9 is placed on the storage rack 4',
The lower spring 14 is compressed in response to the weight of the lid 9', allowing the drive rod 15 to move downward and causing the shielding plate 1 to move downward.
0 is rotated about its fulcrum shaft 17 to shield the space between both side plates. On the other hand, when the load from the lid 9 is removed, the driving rod 15 moves upward due to the biasing force of the spring 14, and, contrary to the above, the shielding plate is rotated toward the open side using the fulcrum shaft 17 as a fulcrum.
この構成によれば、前記特開昭58−182593号公
報のものが保管ラツクの上下からしか水の侵入が
ないのに対し、開状態では上下及び横方向から水
の侵入が起こり、それだけ燃料の温度上昇が小さ
くなり、良好な燃料保管状態を得ることができる
と共に、遮蔽板を閉じ、蓋をした状態では水の侵
入は下方のみで極めて小さく、崩壊熱により燃料
集合体の昇温を扶ける有利さがある。 According to this structure, water intrudes only from the top and bottom of the storage rack in the storage rack disclosed in JP-A-58-182593, but in the open state, water intrudes from the top and bottom and from the sides, and the fuel is reduced accordingly. Temperature rise is small, making it possible to obtain good fuel storage conditions, and when the shielding plate is closed and the lid is closed, water intrusion is extremely small only in the downward direction, and decay heat helps to increase the temperature of the fuel assembly. There is an advantage.
次に上記構成の保管ラツク4′を用いて漏洩検
査をする方法を第5図、第6図と共に説明する。 Next, a method for performing a leakage test using the storage rack 4' having the above structure will be explained with reference to FIGS. 5 and 6.
遮蔽板10は保管ラツク4′に取り付けられて
おり、水採集のためのポンプ6、ホース5の付設
された蓋9′の自重によつて開閉することは前述
の通りであり、通常の保管時では開状態にある。 The shielding plate 10 is attached to the storage rack 4', and is opened and closed by the weight of the lid 9' to which the pump 6 and hose 5 for water collection are attached, as described above, and during normal storage. Now it's open.
そこで、燃料集合体1を前記同様、取扱工具2
によつて把持し、ホイスト3で保管ラツク4′内
へ挿入する。この状態では遮蔽板10は開かれ、
燃料集合体1は保管可能である。そして、次にホ
イスト3を利用して蓋9′を保管ラツク4′上に載
せると、その自重により遮蔽板10は閉鎖され
る。(第6図参照)
かくて、この状態で燃料集合体1の崩壊熱によ
り、燃料被覆管内の核分裂生成物が水に溶出する
のを持ち、ポンプ6、ホース5を介してポリビン
7に水を採集し、繭後は前述の場合と同様、水分
析器を使用して核分裂生成物の存否を確認する。 Therefore, the fuel assembly 1 is moved to the handling tool 2 as described above.
and insert it into the storage rack 4' using the hoist 3. In this state, the shielding plate 10 is opened,
The fuel assembly 1 can be stored. Then, when the lid 9' is placed on the storage rack 4' using the hoist 3, the shielding plate 10 is closed by its own weight. (See Figure 6) In this state, the fission products in the fuel cladding tube are eluted into water due to the decay heat of the fuel assembly 1, and water is pumped into the polybin 7 via the pump 6 and hose 5. After collecting and cocooning, use a water analyzer to confirm the presence or absence of fission products, as in the case described above.
なお、本実施例では、燃料集合体1を保管する
ときには、被覆管を開くため、プール水の循環が
良くなり、良好な保管状態が得られる。 In this embodiment, when the fuel assembly 1 is stored, the cladding tube is opened, which improves the circulation of pool water and provides a good storage condition.
なお、以上は保管ラツク4、水採集機構Bが
夫々1個の場合であるが、これら保管ラツク4、
水採集機構Bは複数であつてもよく、この場合に
は第4図に図示する如く、複数の保管ラツク4、
水採集機構Bを並置し、これらの全部又は部分分
割して蓋9を共通とし、これに突起部を所要数設
けて1個又は少ない吊下移動機構Aを用いて操作
するようにする。 Note that the above is a case where there is one storage rack 4 and one water collection mechanism B, but these storage racks 4,
There may be a plurality of water collection mechanisms B, in which case there are a plurality of storage racks 4, as shown in FIG.
The water collecting mechanisms B are arranged side by side, all or part of them are divided to make a common lid 9, and a required number of protrusions are provided on the lid 9 so that it can be operated using one or a small number of hanging moving mechanisms A.
(発明の効果)
本発明装置は以上のように保管ラツクに対し水
採集機構を付設した蓋を載せるだけで漏洩検査作
業を行えるようにしたものであり、特に保管ラツ
クの周壁を開閉自在の遮蔽板によつて形成し、蓋
の開閉に連動して該遮蔽板を開閉せしめるように
構成したことにより、燃料集合体を保管ラツクか
ら更に別の検査装置まで移動させる必要がなく、
燃料集合体の保管を可能としつつ、該場所で閉鎖
空間を形成するだけで容易に漏洩検査ができ、検
査の簡易化、検査時間の短縮を始めとして検査作
業の作業性が著しく改善されるに止まらず、遮蔽
板開状態では上下及び横方向から水を侵入させ、
それだけ燃料の温度上昇を小さくして燃料保管状
態を良好ならしめることができると共に、蓋止状
態では遮蔽板を閉じ、水の侵入を下方のみとして
崩壊熱により燃料集合体の昇温を扶け、全体とし
て燃料棒被覆管内の昇温、昇圧によるピンホール
等からの核分裂生成物の漏出を促進し、検査効率
を高める効果が期待される。(Effects of the Invention) As described above, the device of the present invention enables leakage inspection work simply by placing a lid equipped with a water collection mechanism on a storage rack. By forming the shielding plate from a plate and opening and closing the shielding plate in conjunction with the opening and closing of the lid, there is no need to move the fuel assembly from the storage rack to another inspection device.
While making it possible to store fuel assemblies, leakage inspection can be easily carried out by simply creating a closed space at the location, which significantly improves the workability of inspection work by simplifying inspections and shortening inspection time. When the shield plate is open, water enters from above and below and from the sides.
This makes it possible to reduce the temperature rise of the fuel and improve the fuel storage condition. In addition, when the lid is closed, the shielding plate is closed, allowing water to enter only in the downward direction, and using decay heat to increase the temperature of the fuel assembly. Overall, the increase in temperature and pressure inside the fuel rod cladding tube promotes the leakage of fission products from pinholes, etc., and is expected to have the effect of increasing inspection efficiency.
第1図及び第2図は本発明に係る検査装置の1
例を示す概要説明図で、第1図は燃料集合体保管
時、第2図は漏洩検査時である。又、第3図イ,
ロ,ハ,ニは前記装置における保管ラツクの1例
で、イは正面図、ロは平面図、ハ,ニハ夫々イに
おけるA−A断面図、B−B断面図である。第4
図は本発明に係る装置の変形例として複数の保管
ラツクを並置した場合を略示図で示す。更に第5
図及び第6図は本発明に係る検査装置を示す概要
図で、第5図は保管時、第6図は漏洩検査時であ
る。第7図は上記装置に使用した保管ラツクの詳
細斜視図、第8図は遮蔽板斜視図である。
1……原子燃料集合体、A……吊下移動機構、
B……水採集機構、2……取扱工具、3……ホイ
スト、4,4′……保管ラツク、5……ホース、
6……ポンプ、7……ポリビン、9,9′……蓋、
10……遮蔽板、41……保管ラツク上部開口、
42……蓋載せ台。
FIG. 1 and FIG. 2 show one of the inspection apparatuses according to the present invention.
These are schematic explanatory diagrams showing examples, in which FIG. 1 shows the fuel assembly during storage, and FIG. 2 shows the state during leakage inspection. Also, Figure 3 A,
B, C, and D are examples of storage racks in the device, in which A is a front view, B is a plan view, C, C, and D are sectional views taken along A-A and B-B in A, respectively. Fourth
The figure schematically shows a variant of the device according to the invention in which a plurality of storage racks are arranged side by side. Furthermore, the fifth
6 and 6 are schematic diagrams showing the inspection device according to the present invention, FIG. 5 during storage, and FIG. 6 during leakage inspection. FIG. 7 is a detailed perspective view of a storage rack used in the above apparatus, and FIG. 8 is a perspective view of a shielding plate. 1... Nuclear fuel assembly, A... Hanging movement mechanism,
B... Water collection mechanism, 2... Handling tool, 3... Hoist, 4, 4'... Storage rack, 5... Hose,
6...pump, 7...polybin, 9,9'...lid,
10... Shielding plate, 41... Storage rack upper opening,
42...Lid mounting stand.
Claims (1)
する蓋を備えて内部に原子燃料集合体を収納保管
する保管ラツクと、該保管ラツクの蓋に取りつけ
られ、上方へ延びるホースならびにポンプ手段を
有して保管ラツク内の水を採集する水採集機構
と、前記保管ラツクの上部開口を通じて原子燃料
集合体を該保管ラツク内へ移動挿入する原子燃料
集合体の吊下移動機構を具備して構成され、か
つ、前記保管ラツクの周壁面が一部において、そ
の上部開口を蓋止することによつて閉鎖される開
閉可能な遮蔽板により形成されていることを特徴
とする原子燃料集合体の漏洩検査装置。1. A storage rack that is surrounded by a peripheral wall and has a lid that opens and closes an upper opening for storing nuclear fuel assemblies inside, and a hose that is attached to the lid of the storage rack and extends upward, and a pump means. a water collection mechanism for collecting water in the storage rack; and a suspension movement mechanism for the nuclear fuel assembly for moving and inserting the nuclear fuel assembly into the storage rack through the upper opening of the storage rack. , and a part of the peripheral wall surface of the storage rack is formed by an openable and closable shielding plate that is closed by covering an upper opening of the storage rack. Device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57203865A JPS5994098A (en) | 1982-11-19 | 1982-11-19 | Method and device for inspecting leakage of nuclear fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57203865A JPS5994098A (en) | 1982-11-19 | 1982-11-19 | Method and device for inspecting leakage of nuclear fuel assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5994098A JPS5994098A (en) | 1984-05-30 |
| JPH028279B2 true JPH028279B2 (en) | 1990-02-23 |
Family
ID=16480978
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57203865A Granted JPS5994098A (en) | 1982-11-19 | 1982-11-19 | Method and device for inspecting leakage of nuclear fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5994098A (en) |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS58182593A (en) * | 1982-04-20 | 1983-10-25 | 三菱重工業株式会社 | Nuclear fuel failure inspecting device |
-
1982
- 1982-11-19 JP JP57203865A patent/JPS5994098A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5994098A (en) | 1984-05-30 |
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