JPS59107296A - Fuel exchanging facility of pressure tube type reactor - Google Patents

Fuel exchanging facility of pressure tube type reactor

Info

Publication number
JPS59107296A
JPS59107296A JP57218012A JP21801282A JPS59107296A JP S59107296 A JPS59107296 A JP S59107296A JP 57218012 A JP57218012 A JP 57218012A JP 21801282 A JP21801282 A JP 21801282A JP S59107296 A JPS59107296 A JP S59107296A
Authority
JP
Japan
Prior art keywords
fuel
rod
fuel rod
reactor
storage box
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.)
Pending
Application number
JP57218012A
Other languages
Japanese (ja)
Inventor
光則 佐藤
雅彦 田辺
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP57218012A priority Critical patent/JPS59107296A/en
Publication of JPS59107296A publication Critical patent/JPS59107296A/en
Pending 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

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  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (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】 〔発明の利用分野〕 本発明は圧力管型原子炉の燃料交換設備に関するもので
、特に原子炉建屋の耐震性向上、燃料交換のためのスペ
ースの合理化並びに燃料交換設備の簡素化及び取扱の容
易化を図った燃料交換設備に関する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to fuel exchange equipment for pressure tube nuclear reactors, and in particular to improvement of earthquake resistance of reactor buildings, rationalization of space for fuel exchange, and fuel exchange equipment. This invention relates to fuel exchange equipment that is simpler and easier to handle.

〔従来技術〕[Prior art]

圧力管型原子炉の建屋構造のうち燃料交換機及び燃料移
送専用スペース部分の従来例を第1図に示す。この図に
おいて、1は原子炉、2はその圧力管、3は原子炉格納
容器、4は基礎マット、5は基礎マット4中に設けた地
下水路、6は使用済燃料貯蔵プール、7はそれらに満た
された水を示す0原子炉1の下方に敷設された軌道上を
図面において水平左右方向に移動する走行台車8に乗っ
て直角水平方向に移動する横行台車9に支持されている
燃料交換機10//i圧力管2に結合するスナウト11
、燃料棒(図示せず)を昇降させるグラブ(図示せず)
、燃料棒を収容するマガジン(図示せず)、該燃料棒と
下部遮蔽プラグ(図示せず)を結合あるいは分離する燃
料遮蔽プラグ着脱装置(図示せず)、燃料交換機10へ
の給水及び使用済燃料の崩壊熱を除去する給水冷却系(
図示せず)を備えている。
FIG. 1 shows a conventional example of a space dedicated to a fuel exchanger and fuel transfer in the building structure of a pressure tube nuclear reactor. In this figure, 1 is a nuclear reactor, 2 is its pressure pipe, 3 is a reactor containment vessel, 4 is a foundation mat, 5 is an underground waterway provided in the foundation mat 4, 6 is a spent fuel storage pool, and 7 is their A refueling machine supported by a transverse truck 9 that moves horizontally at right angles on a traveling truck 8 that moves horizontally left and right in the drawing on a track laid below the reactor 1. 10//i Snout 11 coupled to pressure pipe 2
, a grab (not shown) that raises and lowers the fuel rod (not shown)
, a magazine (not shown) that accommodates the fuel rods, a fuel shielding plug attaching/detaching device (not shown) that connects or separates the fuel rods and the lower shielding plug (not shown), water supply to the fuel exchanger 10, and a used fuel rod. Feed water cooling system that removes the decay heat of fuel (
(not shown).

燃料交換を行うときには、燃料交換機10内のマガジン
に新燃料棒及び新シールプラグを収容し、指定の圧力管
2の下部まで台車8.9によシ移動し位置決めを行った
後、スナウト11を該圧力管2に結合する。次に該圧力
管2内に挿入されている使用済シールプラグ及び使用済
燃料棒及び下部遮蔽プラグをグラブによシ引抜き、燃料
交換機10内のマガジンに収容されている新燃料棒及び
新シールプラグと各々交換する。その後スナウト11を
圧力管2よシはすし、台8.9により燃料交換機10を
出入ボート12の上部まで移動する。次いで燃料交換機
10の下部と出入ボート12を結合した後、上部の燃料
棒出入グリッパ13で燃料交換機10のマガジン内の使
用済燃料棒及びシールプラグを摘み、該出入ポート12
を経て水中移送台車14に移す0その後、水中移送台車
14を基礎マット4中に設けられた地下水路5内の水7
中を移動させ、水中移送台車14内の使用済燃料棒及び
シールプラグを受渡しボート15を経由して使用済燃料
貯蔵プール6の水7中へ移す。、 しかしながら上記従来技術には下記のような欠点がある
When performing fuel exchange, new fuel rods and new seal plugs are stored in the magazine in the fuel exchanger 10, moved to the lower part of the designated pressure pipe 2 by the trolley 8.9, and after positioning, the snout 11 is It is connected to the pressure pipe 2. Next, the spent seal plugs, spent fuel rods, and lower shielding plugs inserted into the pressure pipe 2 are pulled out by a grab, and the new fuel rods and new seal plugs housed in the magazine in the fuel exchanger 10 are removed. and exchange each. Thereafter, the snout 11 is moved through the pressure pipe 2, and the refueling machine 10 is moved to the upper part of the access boat 12 using the platform 8.9. Next, after connecting the lower part of the fuel exchanger 10 and the inlet/outlet boat 12, the upper fuel rod inlet/outlet gripper 13 grips the spent fuel rods and seal plugs in the magazine of the fuel exchanger 10, and then removes the spent fuel rods and seal plugs from the inlet/outlet port 12.
After that, the underwater transfer cart 14 is transferred to the water 7 in the underground waterway 5 provided in the foundation mat 4.
The spent fuel rods and seal plugs in the underwater transfer vehicle 14 are transferred to the water 7 of the spent fuel storage pool 6 via the delivery boat 15. However, the above conventional technology has the following drawbacks.

(1)基礎マット4中に地下水路5を設けていることは
、構造、強度及び建設施工上決して好ましいことではな
い。
(1) Providing an underground waterway 5 in the foundation mat 4 is not at all preferable in terms of structure, strength, and construction work.

(2)燃料交換機10は前記の如き諸機器を内蔵してい
るので、その高さは取扱う燃料棒の長さのはホ3.5倍
である必要があり、出入ボート12の存在と相俟って、
第1図の高さHを小さくすることができないので建屋の
耐震性が悪くなシ、また建屋のコンノくクト化が難しい
(2) Since the fuel exchanger 10 incorporates the various devices described above, its height needs to be 3.5 times the length of the fuel rods it handles, and this, combined with the presence of the access boat 12, So,
Since the height H in Figure 1 cannot be reduced, the earthquake resistance of the building is poor and it is difficult to make the building compact.

(3)前述したような各種の機器から機器への燃料棒の
移し換えのステップを多段階行わねばならないので燃料
交換時間の短縮化が難しいのみならず、交換作業中に燃
料棒落下事故が発生する機会が多くなると共に、ステッ
プ毎に要する設備が多数となり燃料交換設備全体が複雑
化する。
(3) As the above-mentioned steps for transferring fuel rods from one device to another must be performed in multiple stages, it is not only difficult to shorten the fuel exchange time, but also accidents that occur when fuel rods fall during the exchange work. As the number of opportunities for fuel exchange increases, a large number of equipment are required for each step, making the entire fuel exchange facility complex.

〔発明の目的〕[Purpose of the invention]

本発明は従来の前記欠点に鑑み、基礎マットを構造、強
度及び施工上合理的なものにし、また建屋内の燃料交換
設備の占める高さを小さくして建屋の耐震性向上及びコ
ンパクト化を図シ、燃料交換のための所要時間の短縮及
びその作業の簡単化、並びに燃料交換設備の簡素化を図
るととの可能な圧力管式原子炉の燃料交換設備を提供す
ることを目的とする。
In view of the above-mentioned drawbacks of the conventional technology, the present invention aims to improve the earthquake resistance and make the building more compact by making the foundation mat rational in terms of structure, strength, and construction, and by reducing the height occupied by the fuel exchange equipment inside the building. Another object of the present invention is to provide fuel exchange equipment for a pressure tube nuclear reactor that can shorten the time required for fuel exchange, simplify the work, and simplify the fuel exchange equipment.

〔発明の概要〕[Summary of the invention]

本発明による圧力管型原子炉の燃料交換設備は原子炉建
屋内に設けられた原子炉の任意の圧力管の直下に位置し
得るような水平二方向の移動の自由度を有する第一の移
動運搬装置、少なくとも水平左右方向に移動し得る上記
第一の移動運搬装置より下位高さに設けられた第二の移
動運搬装置、上記第一の移動運搬装置に支持され任意の
上記圧力管の下端と着脱自在に連結し得る圧力管内に燃
料棒を出入させるだめの燃料棒取扱装置、上記第二の移
動運搬装置に支持され、上記燃料棒取扱装置の下端と着
脱自在に連結されて該燃料棒取扱装置と燃料棒の受授を
行う燃料棒収納箱、及び上記水平に移動する第二の移動
運搬装置及びそれに支持された上記燃料棒収納箱を通過
せしめるように原子炉下方区域と使用済燃料貯蔵プール
とを連絡する搬送口からなることを特徴とする。
The fuel exchange equipment for a pressure tube type nuclear reactor according to the present invention has a first movable system having a degree of freedom of movement in two horizontal directions so that it can be located directly under any pressure pipe of the reactor installed in the reactor building. a second movable conveyance device which is movable in at least horizontal left and right directions and is provided at a lower height than the first movable conveyance device; a lower end of any of the pressure pipes supported by the first movable conveyance device; a fuel rod handling device for moving fuel rods in and out of a pressure pipe that can be detachably connected to the fuel rod; A handling device, a fuel rod storage box for receiving and receiving fuel rods, and a second mobile transportation device that moves horizontally and the fuel rod storage box supported by the reactor lower area and the spent fuel. It is characterized by comprising a transport port that communicates with the storage pool.

〔発明の実施例〕[Embodiments of the invention]

本発明の一実施例を全体的に第2図に示す。 One embodiment of the invention is generally shown in FIG.

この図において第1図中の部分に相当する部分は同じ符
号で示しである。
In this figure, parts corresponding to those in FIG. 1 are designated by the same reference numerals.

第2図において、圧力管型原子炉1の下方に設けられた
軌道上を図の水平左右方向に移動する走行台車8上に乗
って直角水平方向に移動する横行台車9に支持されてい
る燃帰取扱機16は原子炉G圧力管2と結合するスナウ
ト11を有する。また上記軌道の下方に敷設された別の
軌道上を図の水平左右方向に移動する走行台車17に乗
って直角水平方向に移動する横行台車18に燃料棒収納
箱19が支持されている。燃料棒収納箱19の上部は燃
料棒取扱機16の下部と着脱可能になっている。
In FIG. 2, a fuel tank is mounted on a traveling truck 8 that moves in the horizontal left and right directions in the figure on a track provided below the pressure tube reactor 1, and is supported by a transverse truck 9 that moves in the horizontal direction at right angles. The return handling machine 16 has a snout 11 that connects with the reactor G pressure pipe 2. Further, a fuel rod storage box 19 is supported by a traversing truck 18 that moves in a perpendicular horizontal direction while riding on a traveling truck 17 that moves in horizontal left and right directions in the figure on another track laid below the above-mentioned track. The upper part of the fuel rod storage box 19 is detachable from the lower part of the fuel rod handling machine 16.

第3図は燃料棒取扱機16と燃料棒収納箱19の構造の
概要を示した縦断面図であって、両者が結合された状態
を示している。燃料棒取扱機16は、上部に圧力管2と
連結可能なスナウト11を備えており、内部には、燃料
棒20を昇降さぜるチェーン21、燃料棒と下部遮蔽プ
ラグ(不図示)を結合又は分離する燃料遮蔽プラグ着脱
装置(不図示)、分離された下部遮蔽プラグを収納する
ケース22、燃料棒を原子炉から出入させるロッド23
を備えている。ロッド23はモータ24で回転可能な軸
25に固定されたアーム板26の穴に遊嵌し、常時は、
軸25に固定された受台27上に下端が載っている。
FIG. 3 is a vertical sectional view showing the outline of the structure of the fuel rod handling machine 16 and the fuel rod storage box 19, and shows a state in which the two are connected. The fuel rod handling machine 16 is equipped with a snout 11 that can be connected to the pressure pipe 2 at the upper part, and inside is a chain 21 that moves the fuel rods 20 up and down, and a chain 21 that connects the fuel rods and a lower shielding plug (not shown). or a separating fuel shielding plug attaching/detaching device (not shown), a case 22 for storing the separated lower shielding plug, and a rod 23 for moving fuel rods in and out of the reactor.
It is equipped with The rod 23 is loosely fitted into a hole in an arm plate 26 fixed to a shaft 25 that can be rotated by a motor 24.
The lower end rests on a pedestal 27 fixed to the shaft 25.

燃料棒取扱機19は、燃料棒取扱機16の下部管28と
連結可能なスナウト29を備えていると共に、内部には
燃料棒20を昇降させるチェーン30を備えている。
The fuel rod handling machine 19 is equipped with a snout 29 that can be connected to the lower pipe 28 of the fuel rod handling machine 16, and is equipped with a chain 30 for raising and lowering the fuel rods 20 inside.

第4図は、圧力管2と上記スナウト11及び上記の下部
管28とスナウト29を夫々着脱自在に連結する連結部
(第3図のA部)の構造の一例を示す断面図である。同
図中33はスナウト11(29)の上端に設けられた連
結管で、油圧シリンダ32によシ伸長し、圧力管2(又
は下部管28)に嵌入連結可能であシ、31は該連結離
脱用の緊縮バネである。
FIG. 4 is a sectional view showing an example of the structure of a connecting portion (section A in FIG. 3) that removably connects the pressure pipe 2 and the snout 11, and the lower tube 28 and the snout 29, respectively. In the same figure, 33 is a connecting pipe provided at the upper end of the snout 11 (29), which extends by the hydraulic cylinder 32 and can be fitted and connected to the pressure pipe 2 (or lower pipe 28), and 31 is the connecting pipe. This is a tension spring for withdrawal.

第5図は、第3図の線B−Bでとった断面図である。同
図中34はチェーン21の駆動用モータで、燃料棒20
を圧力管に対して出入するには、前記ロッド23と共働
することによって行なわれる。すなわちチェーン21に
は復数個の突起21′ζ21“・・・が設けられ、該突
起21’がロッドの実記23′、燃料棒の突起20′、
20“と交互的に係合し、圧力管2に対する燃料棒の出
入れ操作を行う。
FIG. 5 is a cross-sectional view taken along line BB in FIG. In the figure, 34 is a motor for driving the chain 21, and the fuel rod 20
The movement into and out of the pressure pipe takes place by cooperating with said rod 23. That is, the chain 21 is provided with a plurality of protrusions 21'ζ21"..., and the protrusions 21' correspond to the actual rod 23', the fuel rod protrusion 20',
20'' and performs the operation of inserting and removing the fuel rods into and out of the pressure pipe 2.

なお、燃料棒取扱機16及び燃料棒収納箱19は、これ
らへの給水及び使用済燃料の崩壊熱除去用の給水冷却系
(不図示)を備えている。
The fuel rod handling machine 16 and the fuel rod storage box 19 are equipped with a water supply cooling system (not shown) for supplying water thereto and removing decay heat from the spent fuel.

上記構成において、燃料交換を行うプロセスについて第
6図〜第10図を参照して以下に説明する。
In the above configuration, a process for performing fuel exchange will be described below with reference to FIGS. 6 to 10.

燃料棒取扱機16と燃料収能箱19とが共に横行、走行
可能々ときは、それらの下部管28とスナウト29にて
結合した状態のままで台車8.9及び17.18によシ
指定の圧力管2の下部まで移動し、位置決めを行った後
、スナウト11を該圧力管2に結合する。次にモータ2
4で軸25を回転させてロッド23を第3図の位置から
スナウ)11の直下の位置に回転移動し、チェーン21
を時計回シに駆動すると、その突起21′が第6図の如
くロッド23の突起23′の下側に係合してロッド23
は圧力管2内に挿入され、次にチェーン21を反時計回
シに駆動すると、圧力管2内の使用済燃料棒2oがロッ
ド23と共に引き降ろされ、チェーン21の第2の突起
2工が該燃料棒20の突起20′(第7図)の下側に係
合してこれを支える。ここで燃料遮蔽プラグ着脱装置(
不図示)にょシ該使用済燃料棒20から下部遮蔽プラグ
(不図示)を分離してケース22にこれを収納する。次
いで更にチェーンを反時計回シに駆動すると、下部遮蔽
プラグを分離された使用済燃料棒2o及びロッド23は
更に下シ、第7図の如くロッド23の下端が受台27に
載って突起21′と23′の保合が解かれる状態になる
。この状態においてモータ24で軸25を180°回転
させロッド23を第8図図示の位置まで回転移動させる
。この間、使用済燃料棒20は突起21“で不動に支持
されている。その後、第8図の状態から更にチェーン2
1を反時計回シに駆動すると、該燃料棒2゜は更に下ル
、その突起20“がチェーン21の突起21′で支えら
れる代シに突起20′が突起21“から離れた状態とな
って燃料棒20は第9図の如く下部管28、スナウト2
9から燃料収納箱19内に入シ、その突起20′がチェ
ーン30の突起30′で支持されるに至る。その後、チ
ェーン21.30を反時計回りに駆動することによシ、
突起20“が突起21′から外れた後、遂に使用済燃料
棒20が燃料収納箱19内に第10図の如く完全に収納
されるに至る。
When the fuel rod handling machine 16 and the fuel storage box 19 are both horizontally moving and can be moved, they are connected to the lower pipe 28 and the snout 29, and then moved to the bogies 8.9 and 17.18. After moving to the lower part of the pressure pipe 2 and positioning it, the snout 11 is connected to the pressure pipe 2. Next motor 2
4, rotate the shaft 25 to move the rod 23 from the position shown in FIG.
When driven clockwise, its protrusion 21' engages with the lower side of the protrusion 23' of the rod 23 as shown in FIG.
is inserted into the pressure pipe 2, and then when the chain 21 is driven counterclockwise, the spent fuel rod 2o in the pressure pipe 2 is pulled down together with the rod 23, and the second protrusion 2 of the chain 21 is pulled down. It engages with and supports the lower side of the protrusion 20' (FIG. 7) of the fuel rod 20. At this point, install the fuel shielding plug attachment/detachment device (
A lower shielding plug (not shown) is separated from the spent fuel rod 20 (not shown) and is housed in the case 22. Next, when the chain is further driven counterclockwise, the spent fuel rod 2o and the rod 23 from which the lower shielding plug has been separated are moved further downward, and as shown in FIG. ' and 23' become unconsolidated. In this state, the motor 24 rotates the shaft 25 by 180 degrees to rotationally move the rod 23 to the position shown in FIG. During this time, the spent fuel rod 20 is immovably supported by the protrusion 21''.Then, from the state shown in FIG.
When the fuel rod 1 is driven counterclockwise, the fuel rod 2° is further lowered, and the protrusion 20' is separated from the protrusion 21'' while the protrusion 20'' is supported by the protrusion 21' of the chain 21. The fuel rod 20 is connected to the lower pipe 28 and the snout 2 as shown in FIG.
9 into the fuel storage box 19, and its protrusion 20' is supported by the protrusion 30' of the chain 30. Then, by driving the chain 21.30 counterclockwise,
After the protrusion 20'' is removed from the protrusion 21', the spent fuel rod 20 is finally completely stored in the fuel storage box 19 as shown in FIG.

使用済燃料棒20が燃料棒収納箱19に収容された後、
燃料棒収納箱19のスナウト29を燃料棒取扱機16の
下部管28から切シ離す。
After the spent fuel rods 20 are stored in the fuel rod storage box 19,
The snout 29 of the fuel rod storage box 19 is separated from the lower pipe 28 of the fuel rod handling machine 16.

燃料棒取扱機16から切シ離された燃料棒収納箱19は
、台車17.18により原子炉格納容器3下部壁体に使
用済燃料貯蔵プール6の側部に設けられた搬入口35を
通シ抜けて使用済燃料貯蔵プール6まで移送され、受渡
しボート15によシ格納箱19内の使用済燃料棒20は
所定の貯蔵場所へ移送収容される。搬入口35は原子炉
側扉及び使用済燃料貯蔵プール側扉を備えておシ、使用
済燃料貯蔵プール6の水が原子炉格納容器下部空間35
へ流れ込むのを防く゛ために、台車17.18の通過時
にはどちらか一方の扉は閉じられた状態にしておく。
The fuel rod storage box 19 separated from the fuel rod handling machine 16 is carried by a cart 17.18 through the entrance 35 provided in the lower wall of the reactor containment vessel 3 on the side of the spent fuel storage pool 6. The spent fuel rods 20 in the storage box 19 are transferred to a predetermined storage location by the delivery boat 15. The entrance 35 is equipped with a reactor side door and a spent fuel storage pool side door, so that the water in the spent fuel storage pool 6 flows into the lower space 35 of the reactor containment vessel.
In order to prevent water from flowing into the tank, one of the doors is kept closed when the carts 17 and 18 pass.

新燃料棒の装荷は上記と逆の手順によって行なわれる。Loading of new fuel rods is performed by reversing the above procedure.

以上の構成においては、燃料棒取扱機16の高さは燃料
棒長さのほぼ1.5倍程度、また燃料棒収納箱19の高
さは燃料棒の長さよシ少し長い程度に抑えることができ
るので、4全体として第1図の従来例における高さHに
比して第2図に示す高さH′をかなシ小さくすることが
でき、原子炉建屋の全高を低めることになシ、その耐震
性の向上が図れる0 さらに燃料移送台車17.18及び燃料棒収納箱19を
、従来例と異なり、複数台設置することも可能であシ、
その場合には、なお一層燃料交換時間の短縮化が図れる
0 なお第2図において原子炉格納容器下部の燃料棒収納箱
19の移送路36にも水を張ってもよい0この場合には
燃料移送時における搬入口35の扉の開閉が不要となシ
、更に燃料交換時間を短縮できるという効果があると共
に、燃料交換時の不慮の燃料棒落下に起因する事故の防
止に役立ち、また建屋下部の重量が増加して建屋の耐震
性向上にも役立つ効果がある。
In the above configuration, the height of the fuel rod handling machine 16 can be suppressed to approximately 1.5 times the length of the fuel rods, and the height of the fuel rod storage box 19 can be suppressed to a level slightly longer than the length of the fuel rods. Therefore, as a whole, the height H' shown in FIG. 2 can be made much smaller than the height H in the conventional example shown in FIG. Its earthquake resistance can be improved. Furthermore, unlike the conventional example, it is possible to install multiple fuel transfer carts 17, 18 and fuel rod storage boxes 19.
In that case, the fuel exchange time can be further shortened.In addition, in Fig. 2, water may also be filled in the transfer passage 36 of the fuel rod storage box 19 at the bottom of the reactor containment vessel. It is not necessary to open and close the door of the loading port 35 during transfer, and it has the effect of shortening the fuel exchange time. It also helps prevent accidents caused by accidental dropping of fuel rods during fuel exchange, and This has the effect of increasing the weight of the building and improving the earthquake resistance of the building.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、圧力管型原子炉の燃料交換設備が簡素
化されると共傾燃料交換作業プロセスが簡単化され、燃
料交換時間が短縮されるばかシでなく、作業中の燃料棒
落下事故の発生する機会を少くすることができる。また
基礎マット中に地下水路を設ける必要がないのでその構
造、強度、建設施工に有利であり、また燃料取扱装置及
び燃料収納箱の高さは燃料棒長さに比べてそれ程大きい
ことを要しないから、燃料交換に要するスペースの高さ
を従来よシも小さくすることが可能であって、このため
建屋の耐震性の・向上及びコンパクト化を図ることがで
きる。
According to the present invention, when the refueling equipment of a pressure tube reactor is simplified, the co-inclined refueling work process is simplified, the refueling time is shortened, and the fuel rods fall during the work. The chances of an accident occurring can be reduced. In addition, there is no need to provide an underground waterway in the foundation mat, which is advantageous for its structure, strength, and construction work, and the height of the fuel handling device and fuel storage box does not need to be so large compared to the length of the fuel rods. Therefore, the height of the space required for fuel exchange can be made smaller than before, and as a result, the earthquake resistance of the building can be improved and the building can be made more compact.

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

第1図は、圧力管型原子炉の建屋内の燃料交換機及び燃
料移送専有スペース部分の従来例を示す。 第2図は、本発明の一実施例における圧力管型原子炉の
建屋内の燃料交換用の機器及び燃料移送スペース部分を
示す。第3図は、本発明の一実施例における燃料棒取扱
機及び燃料棒収納箱の概要構造を示し、第4図は第3図
のA部の詳細を、また第5図は第3図のB−B断面を示
す。第6図〜第io図は燃料棒取扱機及び燃料ゝ− 棒収納箱の作動状態を示す。 1・・・圧力管型原子炉 2・・・圧力管3・・・原子
炉格納容器 4・・・基礎マット5・・・地下水路  
  6・・・使用済燃料貯蔵プール8・・・走行台車 
   9・・・横行台車10・・・燃料交換機  11
・・スナウト12・・・出入ボート  13・・・燃料
棒出入グリッパ14・・・水中移送台車 15・・・受
渡ボート16・・・燃料棒取扱機 17・・・走行台車
18・・・横行台車   19・・・燃料棒収納箱20
・・・燃料棒    21・・・昇降チェーン22・・
・下部遮蔽プラグ収納ケース 23・・・燃料棒出入用ロッド 24・・・モータ    25・・・回転軸26・・・
アーム板   27・・・受台28・・・下部管   
 29・・・スナウト30・・・昇降チェーン 31・
・・バネ32・・・油圧シリンダ 33・・・連結管3
4・・・モータ    35・・・搬入口36・・・移
送路 第2図 第3図 第4図 第5図 第6図 第7図 第8図 第9図 第10図
FIG. 1 shows a conventional example of a fuel exchange machine and a dedicated space for fuel transfer inside a pressure tube nuclear reactor building. FIG. 2 shows equipment for fuel exchange and a fuel transfer space inside a building of a pressure tube nuclear reactor according to an embodiment of the present invention. FIG. 3 shows a schematic structure of a fuel rod handling machine and a fuel rod storage box in an embodiment of the present invention, FIG. 4 shows details of part A in FIG. 3, and FIG. A BB cross section is shown. Figures 6 to 10 show the operating conditions of the fuel rod handling machine and the fuel rod storage box. 1...Pressure tube reactor 2...Pressure pipe 3...Reactor containment vessel 4...Foundation mat 5...Underground waterway
6... Spent fuel storage pool 8... Traveling trolley
9...Traversing trolley 10...Fuel exchange machine 11
...Snout 12...Input/output boat 13...Fuel rod in/out gripper 14...Underwater transfer trolley 15...Delivery boat 16...Fuel rod handling machine 17...Traveling trolley 18...Transverse trolley 19...Fuel rod storage box 20
... Fuel rod 21 ... Lifting chain 22 ...
・Lower shielding plug storage case 23...Fuel rod entry/exit rod 24...Motor 25...Rotating shaft 26...
Arm plate 27... pedestal 28... lower tube
29...Snout 30...Elevating chain 31.
...Spring 32...Hydraulic cylinder 33...Connecting pipe 3
4...Motor 35...Inlet port 36...Transfer path Fig. 2 Fig. 3 Fig. 4 Fig. 5 Fig. 6 Fig. 7 Fig. 8 Fig. 9 Fig. 10

Claims (1)

【特許請求の範囲】[Claims] 原子炉建屋内に設けられた圧力管型原子炉の任意の圧力
管の直下に位置し得るような水平二方向の移動の自由度
を有する第一の移動運搬装置、少なくとも水平左右方向
に移動し得る上記第一の移動運搬装置よシ下位高さに設
けられた第二の移動運搬装置、上記第一の移動運搬装置
に支持された任意の上記圧力管の下端と着脱自在に連結
し得る圧力管内に燃料を出入するための燃料棒取扱装置
、上記第二の移動運搬装置に支持され上記燃料取扱装置
の下端と着脱自在に連結されて該燃料棒取扱装置と燃料
棒の受授を行う燃料棒収納箱、及び上記水平に移動する
第二の移動運搬装置及びそれに支持された上記燃料収納
箱を通過せしめるように建屋内の原子炉下方区域と使用
済燃料貯蔵プールとを連絡する搬送口からなることを特
徴とする圧力管型原子炉の燃料交換設備。
A first mobile transport device having a degree of freedom of movement in two horizontal directions, which can be located directly under any pressure pipe of a pressure tube type nuclear reactor installed in a reactor building; a second movable conveyance device installed at a lower level than the first movable conveyance device, which can be removably connected to the lower end of any of the pressure pipes supported by the first movable conveyance device; A fuel rod handling device for moving fuel in and out of the pipe; a fuel rod handling device supported by the second mobile transport device and detachably connected to the lower end of the fuel handling device to receive and receive fuel rods from the fuel rod handling device; a rod storage box, and the horizontally movable second mobile transport device and the fuel storage box supported thereon from a transfer port connecting the lower reactor area in the building and the spent fuel storage pool. Fuel exchange equipment for a pressure tube nuclear reactor, which is characterized by:
JP57218012A 1982-12-13 1982-12-13 Fuel exchanging facility of pressure tube type reactor Pending JPS59107296A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57218012A JPS59107296A (en) 1982-12-13 1982-12-13 Fuel exchanging facility of pressure tube type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57218012A JPS59107296A (en) 1982-12-13 1982-12-13 Fuel exchanging facility of pressure tube type reactor

Publications (1)

Publication Number Publication Date
JPS59107296A true JPS59107296A (en) 1984-06-21

Family

ID=16713238

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57218012A Pending JPS59107296A (en) 1982-12-13 1982-12-13 Fuel exchanging facility of pressure tube type reactor

Country Status (1)

Country Link
JP (1) JPS59107296A (en)

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