JPS58158594A - Nuclear fuel assembly handling device - Google Patents
Nuclear fuel assembly handling deviceInfo
- Publication number
- JPS58158594A JPS58158594A JP57040156A JP4015682A JPS58158594A JP S58158594 A JPS58158594 A JP S58158594A JP 57040156 A JP57040156 A JP 57040156A JP 4015682 A JP4015682 A JP 4015682A JP S58158594 A JPS58158594 A JP S58158594A
- Authority
- JP
- Japan
- Prior art keywords
- fuel assembly
- rod
- handling device
- nuclear fuel
- rods
- 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.)
- Granted
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
- Load-Engaging Elements For Cranes (AREA)
- Control And Safety Of Cranes (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】
この発明は原子燃料集合体上として加圧水型原子炉の燃
料集合体を定期的々検査又は交換のために炉心から出し
入れするだめの取扱い装置の改良に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an improvement in a handling device for moving fuel assemblies of a pressurized water reactor into and out of a reactor core for periodic inspection or replacement.
第１図イ、口、ハは加圧水型原子炉の燃料集合体Ａの正
面、上部ノズルＢの−Ｆ面および下部ノズルＣの下面を
それぞれ示すものであるが、この種燃料集合体Ａは、一
般に下部ノズルＣの一対角線上の脚部に設けたピン挿通
孔Ｃ７を下部炉心板り上のピンＤ、に嵌合させて、多数
体のものが僅かな間隙（約１ｍ〜２問）をおいて下部炉
心板り上に配列され、上方においては冬休の上部ノズル
Ｂの四周に取付けたリーフスプリングＳを圧迫する状態
に上部炉心板（図示せず）によりおおわれて炉心体Ａを
炉心内から出し入れする際には、イ図鎖紳のようにロー
ドセル３を介してクレーン４のワイＡの上部ノズルＢの
中に差し込み、これを開いて下端のフック２ａを上部ノ
ズルＢの上縁に掛は止め、燃料集合体Ａを吊り上げたり
、吊り降ろしたりしており、その際ロードセル３によっ
てクレーンに加わる荷重を検出し作業の安全を図るよう
にしている。Figure 1 A, C, and C show the front side of the fuel assembly A of a pressurized water reactor, the -F plane of the upper nozzle B, and the lower side of the lower nozzle C, respectively. In general, the pin insertion hole C7 provided on the leg on one diagonal of the lower nozzle C is fitted into the pin D on the lower core plate, and a large number of nozzles are inserted with a small gap (approximately 1 m to 2 holes). The upper core plate (not shown) presses the leaf springs S attached to the four circumferences of the upper nozzle B during winter break, and the core body A is placed inside the core. When loading and unloading from the crane, insert the load cell 3 into the upper nozzle B of wire A of the crane 4 as shown in Figure A, open it, and hook the hook 2a at the lower end to the upper edge of the upper nozzle B. The crane is stopped and the fuel assembly A is lifted or lowered, and at this time a load cell 3 detects the load applied to the crane to ensure work safety.
しかし、このものでは取扱い装置１の上方に一つのロー
ドセル３を配設して燃料集合体Ａを吊り下げる形式をと
っているために、クレーン４にかかる総荷重（集合体（
約５００に９）や取扱い装置の重量および摩さつ力など
）しか検出することができず、燃料集合体Ａがどんな状
態にあるかを知ることができない、。However, in this device, one load cell 3 is disposed above the handling device 1 to suspend the fuel assembly A, so the total load (the assembly (
500 to 9), the weight of the handling equipment, the grinding force, etc.), and it is not possible to know what condition the fuel assembly A is in.
例えば、燃料集合体Ａを出し入れする際、第２図イ、口
のように燃料集合体への一部の支持格子Ｅが隣りの集合
体の支持格子に引掛ったり又は下部ノズルＣの一方のビ
ン挿通孔ｃｌけ下部炉心板りのビンへに整合したが、他
方の挿通孔は整合せず下部ノズルＣの一部がピン島上に
のり上げて、燃料集合体Ａを傾けるよう々原因が存在し
たにし７てもこれを知ることができない。For example, when loading or unloading the fuel assembly A, some of the support grids E of the fuel assembly may get caught on the support grids of the adjacent fuel assembly, or one of the lower nozzles C may Although the bottle insertion hole CL was aligned with the bottle in the lower core plate, the other insertion hole was not aligned and a portion of the lower nozzle C climbed onto the pin island, causing the fuel assembly A to tilt. Even if you were seven years old, you wouldn't be able to know this.
このような状態にあるに拘らず、燃料集合体Ａを無理に
押し込んだり、引き上げたりすれば、支持格子Ｅを破損
１〜たり、燃料棒を損傷したりして炉の市常な運転を妨
げ、また燃料集合体Ａに傾きを生じると片上りになった
側の上部ノズルＢの縁から吊り杆２が外れる恐れがあり
危険を伴う。Regardless of this condition, if the fuel assembly A is forcibly pushed in or pulled out, it may damage the support grid E or damage the fuel rods, interfering with the normal operation of the reactor. Furthermore, if the fuel assembly A is tilted, the hanging rod 2 may come off from the edge of the upper nozzle B on the side that is tilted upward, which is dangerous.
この発明は上記の欠点を改良すべく工夫されたもので、
燃料集合体の出し入れに際し、その支障状態を直ちに検
出して集合体の損傷を未然に防きと共に不測の危険を防
止することを目的とし、燃料集合体を吊持する取扱い装
置として複数の吊り杆を上部杆と下部杆で形成し、各上
部杆と各下部杆とをコイルばねを介して連結し、各下部
杆の途中にはロードセルをそれぞれ配設したことを特徴
とするものである。This invention was devised to improve the above-mentioned drawbacks.
When loading and unloading fuel assemblies, multiple suspension rods are used as a handling device to suspend fuel assemblies in order to prevent damage to the assemblies and prevent unexpected dangers by immediately detecting any hindrance conditions. is formed of an upper rod and a lower rod, each upper rod and each lower rod are connected via a coil spring, and a load cell is disposed in the middle of each lower rod.
第３図ないし第５図を参照の上、この発明について説明
すれば、１０は取扱い装置であって、上記のものと同様
に油圧操作のアクチェエータを内蔵した操作箱１１に複
数（図示のものでは４本）の吊り杆１２が−１）の円周
上等間隔に回動可能に垂設されているが、これらの尾り
杆１２け操作箱１１中に枢支される上部杆１２ａと下部
フック１２ｃを有する下部杆１２ｂとで構成されており
、各下部杆１２１）の−上端には第５ ＋＊１のように
ばね箱１３が取付けらｆＬ、そのばね箱１３の中に上部
杆１２ａの下Ｑ：５：部が括１！Ｉ！ＩＩ可能に挿入さ
れ、下部杆１２ａの下端つげとはね箱１３の土壁との間
に所要強さく大体１８００に９ｉｎ程度）のコイルばね
１４が配設され、このコイルにね１４を介して下部杆１
２ａと下部杆］、 ２ ｂとは伸縮可能に連結されてい
る。The present invention will be described with reference to FIGS. 3 to 5. Reference numeral 10 denotes a handling device, which is installed in a plurality of operating boxes 11 (not shown in the drawings) which are equipped with hydraulically operated actuators similar to those described above. Four (4) suspension rods 12 are rotatably hung at equal intervals on the circumference of -1), and the upper and lower rods 12a and 12 are pivotally supported in the operation box 11. A lower rod 12b having a hook 12c is attached to the lower end of each lower rod 121), and a spring box 13 is attached to the upper end of each lower rod 121) as shown in FIG. Lower Q: 5: Part 1! I! A coil spring 14 with a required strength (approximately 1800 mm or 9 inches) is installed between the lower end boxwood of the lower rod 12a and the earthen wall of the spring box 13. Lower rod 1
2a and the lower rod] and 2b are extendably connected.
また、各下部ｆＴ１２ｂの途中にはロードセル１５（容
量０．５ ｔ〜１を程度）がそれぞれ配設されており、
谷ロードセル】５に接続てれた出力取り出し用のコード
１６は操作箱１１を通って制御室に導かれている。In addition, a load cell 15 (capacity approximately 0.5 t to 1) is disposed in the middle of each lower fT12b,
An output output cord 16 connected to the valley load cell 5 is led to the control room through the operation box 11.
そして、操作箱１１ｊロツド１１１％を介してクレーン
のワイヤ１７に懸吊されている。The operation box 11j is suspended from the wire 17 of the crane via the rod 111%.
なお、図中１８ａ、１８ｂけ換作箱１】の下面隅部に設
けられたガイドビンおよび位置決めビンであり、訃た、
１９ａ、１９ｂはばわ箱１３の側部および下部杆１２１
）の上端に設けられた空気孔である。Note that 18a and 18b in the figure are guide bins and positioning bins provided at the bottom corner of the replacement box 1.
19a, 19b are the side and lower rods 121 of the box 13
) is an air hole provided at the upper end of the
上述のような構成のもとに、検査の終了した燃料集合体
又は交換のための燃料集合体を炉心内に収容するに当た
っては、操作箱】１下面のガイドビン１８ａおよび位置
決めビン１８ｂを上部ノズルＢの各対応孔に嵌挿すると
共に複数の吊醸杆１２を上部ノズルＢ中に挿入し、操作
箱１１内のアクチュエータを作動して各吊り杆１２を第
４図点線のように外方に開き、下端フック１２ｃを上部
ノズルＢの四１Ｍ上綾に川け＋）めて燃料集合体を吊り
下げ、これを炉心内の所定の場所に挿入量る。Based on the above-mentioned configuration, when storing a fuel assembly that has been inspected or a fuel assembly for replacement into the reactor core, the guide bin 18a and positioning bin 18b on the lower surface of the operation box 1 are connected to the upper nozzle. At the same time, insert a plurality of suspension rods 12 into the corresponding holes of B, and operate the actuator in the operation box 11 to move each suspension rod 12 outward as shown by the dotted line in Figure 4. Open it, hook the lower end hook 12c to the 41M upper twill of the upper nozzle B, suspend the fuel assembly, and insert it into a predetermined position in the core.
その際、伺らの障害が々ければ各吊りｆｆ−１２上のロ
ードセル１５にけＪ燃料集合体に四速する荷重が均等に
かかつているが、若し、前述のように挿入堝イ９におい
て、一部の支持格子が隣接するものの支持格子に引目十
つたり又は下部ノズルの一部が下部炉心板のビンーヒに
のり一部げたりした際には、その支障を生じた側の吊り
杆１２に作用する荷重が他の側のものより少々くなり、
そのことが当該吊ゆ杆１２上のロードセル１５によって
直ちに検出されることになる。又、吊り下げ状態の燃料
集合体に横向きの力が加わった場合には、その反対側の
荷重が少なく々す、やはりロードセル１５により検出さ
れる。At that time, if there are many obstacles, the load for four speeds will be evenly applied to the J fuel assembly by the load cell 15 on each hanging ff-12, but if the load cell 15 on each hanging ff-12 When some of the support grids are adjacent to each other, or when a part of the lower nozzle sticks to the bottom of the lower core plate and lifts off, the suspension on the affected side The load acting on the rod 12 is slightly smaller than that on the other side,
This will be immediately detected by the load cell 15 on the suspension rod 12. Furthermore, when a lateral force is applied to the suspended fuel assembly, the load on the opposite side is less and is also detected by the load cell 15.
そして、この事実が検出されたときには、クレーンによ
って燃料集合体を上方に吊り戻し、その姿勢を直して再
び吊り降ろすようにする。When this fact is detected, the fuel assembly is lifted back up by a crane, its posture is corrected, and the fuel assembly is lifted down again.
一方、上記のような支障により燃料集合体に傾きが生じ
た場合、これを吊持している吊り杆１２のうち片上りに
なった側の吊り杆１２すなわち荷重の少なくなった側の
吊り杆１２の下端フック１２Ｃが上部ノズルＢの係１ヒ
縁から離れようとするが、その吊り杆１２中間のはね箱
１３内で圧縮状態にあるコイルばね１４が荷重の変化に
応じて伸び下部杆１２ｂを第５図点線矢印のように引き
上げるように作用し、下端フック１２Ｃを上部ノズルＢ
の傾きに追従させその係止縁から離脱しないようにする
。On the other hand, if the fuel assembly is tilted due to the above-mentioned trouble, the suspension rod 12 on the side that is tilted upward, that is, the side with less load, among the suspension rods 12 suspending it, The lower end hook 12C of the upper nozzle B tries to separate from the engagement edge of the upper nozzle B, but the coil spring 14, which is in a compressed state in the spring box 13 located between the suspension rod 12, expands in response to the change in load and moves the lower rod. 12b as shown by the dotted line arrow in FIG.
to prevent it from coming off the locking edge.
この場合、コイルばね１４け第５図のような圧縮形式と
しないで、上部杆１２ａと下部杆１２ｂとを直接連結し
た引張りばねとしても同じである。In this case, instead of compressing the 14 coil springs as shown in FIG. 5, it is also possible to use a tension spring in which the upper rod 12a and the lower rod 12b are directly connected.
なお、燃料集合体を炉心内から吊り上げる場合の作用も
上記の場合と変りないが、この場合には支障を生じた側
のロードセル１５には他のものより大きな荷重が検出さ
れることになる。Note that the effect when lifting a fuel assembly from within the core is the same as in the above case, but in this case, a larger load will be detected on the load cell 15 on the side where the problem has occurred than on the other ones.
以上のようにこの発明によれば、原子燃料集合体を吊持
する取扱い装置として、複数の吊ゆ杆をそれぞれ上部杆
と下部杆とで形成し、各上部杆と各下部杆をコイルばね
を介して連結し、各下部杆の途中にはロードセルをそれ
ぞれ配設したので、炉心内から燃料集合体を出し入れす
る際、燃料集合体を傾けるような状態が生じたにしても
、その状態をロードセルによって直ちに検出することが
でき、燃料集合体の姿勢を直して収容することが可能で
燃料集合体の無理な押し込みや引き抜きを防止できるた
め、支持格子や燃料棒の損傷を未然に防ぐことができ、
まだ各吊り杆は燃料集合体が傾いたにしても上部ノズル
によく追従してこれから離脱せず、不測の危険を防止す
ることができる。As described above, according to the present invention, as a handling device for suspending a nuclear fuel assembly, a plurality of suspension rods are each formed with an upper rod and a lower rod, and each upper rod and each lower rod are connected with coil springs. Since a load cell is installed in the middle of each lower rod, even if the fuel assembly is tilted when taking it in or out of the core, the load cell can detect the condition. The fuel assembly can be detected immediately, and the fuel assembly can be repositioned and stored, preventing the fuel assembly from being pushed in or pulled out by force, thereby preventing damage to the support grid and fuel rods. ,
Even if the fuel assembly is tilted, each hanging rod can closely follow the upper nozzle and will not separate from the upper nozzle, thereby preventing unexpected danger.
第１図イは加圧水型原子炉の燃料集合体の収容状態と従
来の取扱い装置の掛は止め状態を示す仙ｊ面図。
同図口は上部ノズルの上面図。
同図ハは下部ノズルの下面図。
第２図イ、口は燃料集合体に障害の生じたときの謂、四
回。
第３図はこの発明の側面図。
第４図は下面図。
第５図ははね筒部分の断面図。
図中、】０・・・取扱い装置、】１・・・操作箱、１２
・・・吊り杆、】２＆・・・上部杆、１２ｂ・・・下部
杆、Ｉ２ｃ・・・フック、】３・・・ばね箱、１４・・
・コイルばね、１５・・・ロードセル、Ａ・・・燃料集
合体、Ｂ・・・上部ノズル、Ｃ・・・下部ノズル。FIG. 1A is a side view showing a fuel assembly of a pressurized water reactor in a housing state and a conventional handling device in an unlatched state. The opening in the figure is a top view of the upper nozzle. Figure C is a bottom view of the lower nozzle. Figure 2 A shows the so-called four times when a failure occurs in the fuel assembly. FIG. 3 is a side view of the invention. Figure 4 is a bottom view. FIG. 5 is a sectional view of the spring tube portion. In the figure, ]0... handling device, ]1... operation box, 12
...hanging rod,]2&...upper rod, 12b...lower rod, I2c...hook, ]3...spring box, 14...
- Coil spring, 15... Load cell, A... Fuel assembly, B... Upper nozzle, C... Lower nozzle.
Claims (3)
動可能に垂設し、各吊シ杆の下端フックを上部ノズルに
掛は止めて燃料集合体を吊持するものにおいて、上記複
数の吊シ杆を上部杆と下部杆で形成し、各上部杆と各下
部杆とをコイルばねを介して連結し、各下部杆の途中に
はロードセルをそれぞれ配設したことを特徴とする原子
燃料集合体の取扱い装置。(1) In a system in which a plurality of hanging rods are rotatably hung from an operation box connected to a crane, and the lower end hook of each hanging rod is hooked onto the upper nozzle to suspend the fuel assembly, the above-mentioned A plurality of suspension rods are formed by upper rods and lower rods, each upper rod and each lower rod are connected via a coil spring, and a load cell is disposed in the middle of each lower rod. Nuclear fuel assembly handling equipment.
縮ばねとしたことを特徴とする特許請求の範囲第１項記
載の原子燃料集合体の取扱い装置。(2) The nuclear fuel assembly handling device according to claim 1, wherein the coil spring interposed between the upper rod and the lower rod is a compression spring.
張りばねとしたことを特徴とする特許請求の範囲第１項
記載の原子燃料集合体の取扱い装置。(3) The nuclear fuel assembly handling device according to claim 1, wherein the coil spring interposed between the upper rod and the lower rod is a tension spring.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57040156A JPS58158594A (en) | 1982-03-16 | 1982-03-16 | Nuclear fuel assembly handling device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57040156A JPS58158594A (en) | 1982-03-16 | 1982-03-16 | Nuclear fuel assembly handling device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58158594A true JPS58158594A (en) | 1983-09-20 |
| JPS6359117B2 JPS6359117B2 (en) | 1988-11-17 |
Family
ID=12572897
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57040156A Granted JPS58158594A (en) | 1982-03-16 | 1982-03-16 | Nuclear fuel assembly handling device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58158594A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61277086A (en) * | 1985-06-03 | 1986-12-08 | 株式会社日立製作所 | Fuel changer |
| CN103764540A (en) * | 2011-09-02 | 2014-04-30 | 埃尔塞乐公司 | Device for handling a load |
| CN108657943A (en) * | 2018-05-22 | 2018-10-16 | 广东核电合营有限公司 | Spent Fuel Pool dilatation screen work hanging apparatus |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0419522U (en) * | 1990-06-07 | 1992-02-19 |
-
1982
- 1982-03-16 JP JP57040156A patent/JPS58158594A/en active Granted
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61277086A (en) * | 1985-06-03 | 1986-12-08 | 株式会社日立製作所 | Fuel changer |
| CN103764540A (en) * | 2011-09-02 | 2014-04-30 | 埃尔塞乐公司 | Device for handling a load |
| CN108657943A (en) * | 2018-05-22 | 2018-10-16 | 广东核电合营有限公司 | Spent Fuel Pool dilatation screen work hanging apparatus |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6359117B2 (en) | 1988-11-17 |
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