JPH02208599A - Nuclear fuel transfer facility for nuclear reactor - Google Patents
Nuclear fuel transfer facility for nuclear reactorInfo
- Publication number
- JPH02208599A JPH02208599A JP1028750A JP2875089A JPH02208599A JP H02208599 A JPH02208599 A JP H02208599A JP 1028750 A JP1028750 A JP 1028750A JP 2875089 A JP2875089 A JP 2875089A JP H02208599 A JPH02208599 A JP H02208599A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- mast
- fuel assembly
- containment vessel
- nuclear
- 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
Links
- 239000003758 nuclear fuel Substances 0.000 title claims description 13
- 239000000446 fuel Substances 0.000 claims abstract description 82
- 239000000498 cooling water Substances 0.000 claims description 8
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 6
- 238000007689 inspection Methods 0.000 abstract description 3
- 238000012423 maintenance Methods 0.000 abstract description 3
- 238000000034 method Methods 0.000 abstract description 2
- 230000000712 assembly Effects 0.000 description 5
- 238000000429 assembly Methods 0.000 description 5
- 230000032258 transport Effects 0.000 description 5
- 238000010586 diagram Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- NMFHJNAPXOMSRX-PUPDPRJKSA-N [(1r)-3-(3,4-dimethoxyphenyl)-1-[3-(2-morpholin-4-ylethoxy)phenyl]propyl] (2s)-1-[(2s)-2-(3,4,5-trimethoxyphenyl)butanoyl]piperidine-2-carboxylate Chemical compound C([C@@H](OC(=O)[C@@H]1CCCCN1C(=O)[C@@H](CC)C=1C=C(OC)C(OC)=C(OC)C=1)C=1C=C(OCCN2CCOCC2)C=CC=1)CC1=CC=C(OC)C(OC)=C1 NMFHJNAPXOMSRX-PUPDPRJKSA-N 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
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
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〈産業上の利用分野〉
本発明は、格納容器と燃料取扱建屋との間での燃料集合
体の搬送を行うための原料炉用核燃料移送設備に関する
。DETAILED DESCRIPTION OF THE INVENTION <Industrial Application Field> The present invention relates to nuclear fuel transfer equipment for a feedstock reactor for transferring fuel assemblies between a containment vessel and a fuel handling building.
〈従来の技術〉
原子力発電等に代表される原子カプラントにおいては、
原子炉の運転に伴って核燃料を随時交換する必要があり
、このため、一般の原子カプラントにおいては原子炉用
核燃料移送装置を組み込むことが普通である。<Conventional technology> In the atomic couplet represented by nuclear power generation,
It is necessary to replace nuclear fuel at any time during the operation of a nuclear reactor, and for this reason, a nuclear fuel transfer device for a nuclear reactor is usually installed in a general nuclear couplant.
従来の原子炉用核燃料移送設備の概念を表２す第４図に
示すように、格納容器１０１の下部に形成した遮蔽体１
０２の中央部には、炉心１０３を収納する原子炉容器１
０４が設置されており、棒状をなす使用済みの燃料集合
体１０５の保管ブース１０６が形成されたピッＩ−１０
７を有する燃料取扱建屋１０８は、前記格納容Ｎ１０１
の側方にこれと隣接状態で設置されている。遮蔽体１０
２のキャビティ１０９と燃料取扱建屋１０８のビット１
０７とは、燃料移送管１１０を介して連通しており、こ
の燃料移送管１１０の両端部には盲フランジ１１１と隔
離弁１１２とがそれぞれ開閉可能に取付けられている。As shown in FIG. 4 of Table 2, which shows the concept of a conventional nuclear fuel transfer facility for a nuclear reactor, a shield 1 is formed at the bottom of a containment vessel 101.
In the center of 02, there is a reactor vessel 1 that houses the reactor core 103.
Pit I-10 where 04 is installed and a storage booth 106 for rod-shaped used fuel assemblies 105 is formed.
7, the fuel handling building 108 has the storage capacity N101.
It is installed on the side and adjacent to this. Shielding body 10
2 cavity 109 and bit 1 of the fuel handling building 108
07 via a fuel transfer pipe 110, and a blind flange 111 and an isolation valve 112 are attached to both ends of the fuel transfer pipe 110 so as to be openable and closable.
前記格納容器１０１の上端部には原子炉容器１０４のＭ
１１３を搬出入するための旋回クレーン１１４が設置さ
れており、更に遮蔽体１０２上には炉心１０３に対して
燃料集合体１０５を出し入れするための燃料取替クレー
ン１１５が設置されている。一方、燃料取扱建屋１０８
のビット１０７に（よ燃料移送管１１０を介してビット
１０７とキャビティ１０９との間を往復動するコンテナ
１１６を有する燃料移送コンベヤ１１７が設けられ、こ
のコンテナ１１６は垂直な状態と水平な状態とに起倒し
、燃料集合体１０５をビット１０７からキャビティ１０
９へ、或いはキャビティ１０９からビット１０７へと搬
送するようになっている。又、ビット１０７上にはこの
燃料移送コンベヤ１１７のコンテナ１１６との間で燃料
集合体１０５の受は渡しを行う燃料ビットクレーン１１
８が設置されており、ビット１０７内及びキャピテイ１
０９内には冷却水が貯留されている。M of the reactor vessel 104 is located at the upper end of the containment vessel 101.
A swing crane 114 is installed to carry fuel assemblies 113 in and out, and a fuel exchange crane 115 is installed on the shield 102 to carry fuel assemblies 105 in and out of the reactor core 103. On the other hand, fuel handling building 108
The bit 107 is provided with a fuel transfer conveyor 117 having a container 116 that reciprocates between the bit 107 and the cavity 109 via a fuel transfer pipe 110, and the container 116 is in a vertical state and a horizontal state. Raise and lower the fuel assembly 105 from the bit 107 to the cavity 10.
9 or from the cavity 109 to the bit 107. Further, on the bit 107 is a fuel bit crane 11 that receives and transfers the fuel assembly 105 to and from the container 116 of the fuel transfer conveyor 117.
8 is installed in Bit 107 and Capity 1.
Cooling water is stored in 09.
従って、燃料の交換を行う場合には旋回クレーン１１４
を操作して原子炉容器１０４のＭ２Ｏ３を遮蔽体１０２
上に形成された操作床１１９に運び出し、次に燃料取替
クレーン１１５を操作して炉心１０３から使用済みの燃
料集合体１０５を引き上げ、キャビティ１０９内にて起
立状態で待機中のコンテナ１１６内に投入する。しかる
のち、コンテナ１１６は水平状態に倒れ、燃料移送管１
１１を通ってビット１０７内へ移動し、再び起立状態と
なって使用済みの燃料Ｓ合体１０５が燃料ビットクレー
ン１１８に引き上げられろ。そして、燃料ビットクレー
ンン１１８はこの使用済みの燃料集合体１０５を保管ブ
ース１０６へ搬送したのち、新たな燃料集合体１０５を
ビット１０７内にて待機中のコンテナ１１６へ投入する
。コンテナ１１６は新たな燃料集合体１０５の投入後に
再び水平状態に倒れ、燃料移送管１１１を通ってキャビ
ティ１０９内へ移動したのち、起立状態となって新たな
燃料集合体１０５を燃料取替りし一ン１１５に引き渡す
。Therefore, when changing fuel, the swing crane 114
to remove M2O3 from the reactor vessel 104 from the shield 102.
The spent fuel assembly 105 is carried out to the operation floor 119 formed above, and then the fuel exchange crane 115 is operated to pull up the spent fuel assembly 105 from the reactor core 103 and placed in the container 116 that is standing by in the cavity 109. throw into. After that, the container 116 falls horizontally, and the fuel transfer pipe 1
11 and into the bit 107, and the spent fuel S combination 105 is raised again to the upright state and is pulled up to the fuel bit crane 118. Then, the fuel bit crane 118 transports the used fuel assembly 105 to the storage booth 106, and then throws a new fuel assembly 105 into the waiting container 116 inside the bit 107. After the new fuel assembly 105 is inserted, the container 116 falls down again into a horizontal state, moves through the fuel transfer pipe 111 into the cavity 109, and then becomes an upright state and replaces the fuel with the new fuel assembly 105. 115.
そて、燃料取替クレーン１１５は炉心１０３へ新たな燃
料集合体１１５を搬入し、更に旋回クレーン１１４の作
動により蓋１１３が原子炉容器１０４に被せられろ。Then, the refueling crane 115 carries a new fuel assembly 115 into the reactor core 103, and the lid 113 is placed over the reactor vessel 104 by the operation of the swing crane 114.
〈発明が解決しようとする課題〉
第４図に示した従来の原子炉用核燃料移送設備では、燃
料移送管１１０に取付けられた盲フランジ１１１や隔離
弁１１２及び燃料移送コンベヤ１１７等の保守点検作業
の際には、ビット１０７及びキャピテイ１０９内の水抜
き作業が必要であり、給排水に要する時間が非常に長く
掛かる。又、格納容器１０１に燃料取替クレーン１１５
を設ける他に、燃料取扱建屋１０８にも燃料ビットクレ
ーン１１８を設ける必要があり、設備が複雑でコスト増
をもたらす。<Problems to be Solved by the Invention> In the conventional nuclear fuel transfer equipment for a nuclear reactor shown in FIG. In this case, it is necessary to drain water from the bit 107 and the cavity 109, and it takes a very long time to supply and drain water. In addition, a fuel exchange crane 115 is installed in the containment vessel 101.
In addition to providing the fuel bit crane 118 in the fuel handling building 108, it is necessary to provide the fuel bit crane 118, which complicates the equipment and increases costs.
く課題を解決するための手段〉
本発明による原子炉用核燃料移送設備は、原子炉を収納
すると共にキャピテイ内に冷却水が貯留された格納容器
と、この格納容器に隣接して設置され且つ燃料ラックを
収納すると共にビット内に冷却水が貯留された燃料取扱
建屋と、前記キャビティ及び前記ビット上方に敷設され
て前記格納容器と前記燃料取扱建屋とに連通ずる走行案
内レールと、この走行案内レールに沿って前記格納容器
と前記燃料取扱建屋との間を住復駆動する移送台車と、
この移送台車に対して水平な旋回軸回りに起倒自在に枢
支された起倒マストと、先端に燃料集合体を把持し得る
グリッパが装着され且つ前記起倒マストに対し伸縮自在
に取付けられて前記燃料集合体と共に前記起倒プスト内
に引き込まれる伸縮マストをＦ−したものである。Means for Solving the Problems> The nuclear fuel transfer equipment for a nuclear reactor according to the present invention includes a containment vessel that houses a nuclear reactor and in which cooling water is stored, and a containment vessel that is installed adjacent to the containment vessel and that carries fuel. a fuel handling building that houses a rack and has cooling water stored in the bit; a travel guide rail that is laid above the cavity and the bit and communicates with the storage container and the fuel handling building; and the travel guide rail. a transfer trolley that moves back and forth between the containment vessel and the fuel handling building along the
A tilting mast is pivotably supported around a horizontal pivot axis with respect to the transfer cart, and a gripper capable of gripping the fuel assembly is attached to the tip and is telescopically attached to the tilting mast. The telescopic mast that is drawn into the raising/lowering mast together with the fuel assembly is F-.
〈作 用〉
移送台車を格納容器側へ移動させ、起倒マストを起立さ
せた状態で伸縮マストを引き伸ばし、原子炉内の使用済
み燃料集合体をグリッパで把持してこれらを起倒マスト
内へ引き上げろ。そして、起倒マストを水平状態に倒し
て移送台車を走行案内レールに沿って燃料取扱建屋に移
動させたのち、再び起倒マストを垂直に起立させて伸縮
マストを引き伸ばし、使用済みの燃料集合体をビット内
へ搬出する。<Operation> Move the transfer cart to the containment vessel side, extend the telescopic mast with the tilting mast erected, grasp the spent fuel assemblies inside the reactor with grippers, and move them into the tilting mast. Pull it up. After the mast is laid down horizontally and the transfer cart is moved along the travel guide rail to the fuel handling building, the mast is raised vertically again and the telescoping mast is extended to remove the used fuel assembly. is carried out into the bit.
新たな燃料集合体を原子炉へ飛入する場合には、ビット
に保管された新たな燃料集合体をグリッパで掴み、伸縮
マストを縮めて起倒マスト内に燃料集合体を引き入れ、
次に起倒マストを水平に倒して移送台車を格納容Ｎ側へ
移動させ、再び起倒マストを垂直に起立させて伸縮マス
トを引き呻ばし、新たな燃料集合体を原子炉へ送り込む
。When a new fuel assembly is to be flown into the reactor, the new fuel assembly stored in the bit is grabbed with a gripper, the telescoping mast is retracted, and the fuel assembly is pulled into the tilting mast.
Next, the hoisting mast is laid down horizontally to move the transfer cart to the storage volume N side, and the hoisting mast is made to stand vertically again and the telescopic mast is pulled and contracted to send a new fuel assembly into the reactor.
く実 施 例〉
本発明による原子炉用核燃料移送設備の一実施例の概略
構造を表す第１図及びその■−■矢視断面構造を表す第
２図及び起倒マストを倒した状態におけるその右側面形
状を表す第３図に示すように、格納容器１１の下部に形
成した遮蔽体１２の中央部には、炉心１３を収納する原
子炉容Ｎ１４が設置されており、棒状をなす使用済みの
燃料集合体１５の保管ブース１６が形成されたビット１
７を有する燃料取扱建屋１８は、前記格納容器１１の側
方にこれと隣接状態で設置されている。遮蔽体１２のキ
ャビティ１９と燃料取扱建屋１８のビット１７とにはそ
れぞれ冷却水が貯留されており、これらキャビティ１９
及びピッＩ・１７の上方には、遮蔽体１２と燃料取扱建
屋１８とに連通ずるハツチ２０が設けられている。この
ハツチ２０の両端部に（よ当該ハツチを開閉するための
吊上げ蓋２１と己蔽扉２２とが付設されている。又、前
記格納容器１１の上端部には原子炉容諸１４の蓋２３を
搬出入したり、或いは吊上げ蓋２１を昇降するため旋回
クレーン２４が設置されており、更に燃料取扱建屋１８
の上端部には遮蔽扉２２を開閉したり、或いは燃料集合
体１５をこの燃料取扱建屋１８外に対して搬出入するた
めの天井クレーン２５が設置されている。又、前記ハツ
チ２０を貫通して格納容＠ｇ１１と燃料取扱建屋１８と
に跨がるように敷設された走行案内レール２６上には、
移送台車２７が往復動自在に乗せられており、この移送
台車２７には走行案内レール２６と直角な方向に当該移
送台車２７上を移動するサドル２８が搭載されている。Embodiment Example FIG. 1 shows a schematic structure of an embodiment of a nuclear fuel transfer facility for a nuclear reactor according to the present invention, and FIG. As shown in FIG. 3, which shows the shape of the right side, a reactor volume N14 that houses the reactor core 13 is installed in the center of the shield 12 formed at the bottom of the containment vessel 11. bit 1 in which a storage booth 16 for a fuel assembly 15 is formed.
A fuel handling building 18 having a fuel handling building 7 is installed on the side of the containment vessel 11 and adjacent thereto. Cooling water is stored in the cavity 19 of the shield 12 and the bit 17 of the fuel handling building 18, respectively.
A hatch 20 communicating with the shield 12 and the fuel handling building 18 is provided above the pit I-17. A lifting lid 21 and a self-shielding door 22 are attached to both ends of the hatch 20 for opening and closing the hatch.Furthermore, at the upper end of the containment vessel 11, a lid 23 of the reactor body 14 is attached. A swing crane 24 is installed to carry in and out the fuel and to lift and lower the lifting lid 21.
An overhead crane 25 is installed at the upper end of the fuel handling building 18 for opening and closing the shield door 22 or for transporting the fuel assembly 15 into and out of the fuel handling building 18. In addition, on the travel guide rail 26 that is laid so as to penetrate the hatch 20 and straddle the storage space @g11 and the fuel handling building 18,
A transfer carriage 27 is mounted on the transfer carriage 27 so as to be able to reciprocate, and a saddle 28 is mounted on the transfer carriage 27, which moves on the transfer carriage 27 in a direction perpendicular to the traveling guide rail 26.
このサドル２８には水平な起倒軸２９を中心に起倒自在
な起倒マスト３０が取付けられている。そして、この起
倒マスト３０と移送台車２７との間には、起倒マスト３
０を水平状態と垂直状態とに切換えろためのマスト起倒
装置３１が介装されている。起倒マスト３０には本実施
例では二段伸縮式の伸縮マス１−３２．３３が摺動自在
に嵌合されており、更に起倒マスト３０の上端に組込ん
だ巻上げ装置３４に連結されるワイヤ３５には、燃料集
合体１５の上部を把持するグリッパ３６が固定されてい
る。A tilting mast 30 is attached to the saddle 28 and is capable of being raised and lowered about a horizontal tilting shaft 29. And, between this raising mast 30 and the transfer truck 27, the raising mast 3
A mast raising/lowering device 31 is provided to switch the mast 0 between a horizontal state and a vertical state. In this embodiment, a two-stage telescoping type telescoping mass 1-32.33 is slidably fitted to the hoisting mast 30, and is further connected to a hoisting device 34 built into the upper end of the hoisting mast 30. A gripper 36 that grips the upper part of the fuel assembly 15 is fixed to the wire 35 .
従って、巻上げ装置３４により燃料集合体１５を掴んだ
グリッパ３６をワイヤ３５と共に引上げると、グリッパ
３６がまず小径の方の伸縮マスト３２の上端部に係止し
てこの伸縮マスト３２も途中から同時に引上げ、更に小
径の方の伸縮マスト３２が大径の方の伸縮マスト３３の
上端部に係止し、最終的には伸縮マスト３２，３３とも
ども燃料集合体１５が起倒マスト３０内に引き入れられ
ろようになっている。Therefore, when the gripper 36 that has gripped the fuel assembly 15 is pulled up together with the wire 35 by the hoisting device 34, the gripper 36 first locks onto the upper end of the telescopic mast 32 with a smaller diameter, and this telescopic mast 32 also moves from the middle at the same time. As the fuel assembly 15 is pulled up, the smaller diameter telescopic mast 32 is locked to the upper end of the larger diameter telescopic mast 33, and finally both the telescopic masts 32, 33 and the fuel assembly 15 are pulled into the vertical mast 30. It's getting dark.
なお、前記起倒マスト３０には燃料集合体１５の崩壊熱
による温度上昇を抑えるための図示しない冷却手段が組
込まれ、更に放射線防護処置が必要に応じて施されてい
る。又、この起倒マスト３０の下端部には、当該起倒マ
スト３０の下＠開口部分を開閉するための開閉Ｍ３７を
有する蓋開閉装置３８が組付けられている。Note that a cooling means (not shown) is incorporated in the raising mast 30 to suppress a temperature rise due to decay heat of the fuel assembly 15, and further radiation protection measures are taken as necessary. Further, a lid opening/closing device 38 having an opening/closing M37 for opening and closing the lower opening portion of the raising mast 30 is assembled to the lower end portion of the raising mast 30.
使用済みの燃料集合体１５を炉心１３から燃料取扱建屋
１８の保管ブース１６へ搬送する場合には、まず旋回ク
レーン２４を操作して原子炉容器１４のｉ２３を遮蔽体
１２の上面に形成された作業床３９に運び上げ、次に移
送台車２７を炉体１３の上方へ移動して巻上げ装置３４
を作動させ、グリッパ３６により所定の使用済みの燃料
集合体１５を掴む。When transporting the spent fuel assembly 15 from the reactor core 13 to the storage booth 16 in the fuel handling building 18, first operate the swing crane 24 to remove the i23 of the reactor vessel 14 from the top surface of the shield 12. The transport cart 27 is then moved above the furnace body 13 and the hoisting device 34 is moved to the work floor 39.
is activated, and a predetermined used fuel assembly 15 is gripped by the gripper 36.
そして、今度は掴んだ燃料集合体１５を伸縮マスト３２
．３３と共に起倒マスト３０内へ引き上げ、蓋開閉装置
３８を作動して開閉蓋３７により起倒マスト３０内を密
閉する。しかるのち、マスト起倒装置３１を作動して起
倒軸２９を中心に起倒マスト３０を水平状態に倒しく第
３図中、二点鎖線参照）、更に吊上げ盃２１と遮蔽扉２
２とを上方に引き上げてハツチ２０を開き、移送台車２
７を走行案内レール２６に治ってハツチ２０から燃料取
扱建屋１８側へ移送させ、保管ブース１６の上方で停止
させる。そして、再びマスト起倒装置３１を作動して起
倒軸２９を中心に起倒マスト３０を垂直状態に起立させ
、この状態で巻上げ装置３４を作動して起倒マスト３０
内の燃料集合体１５を吊り下ろし、保管ブース１６内へ
投入する。Then, this time, the grabbed fuel assembly 15 is placed on the telescopic mast 32.
．． 33 into the inside of the raising mast 30, and the lid opening/closing device 38 is activated to seal the inside of the raising mast 30 with the opening/closing lid 37. Thereafter, the mast raising/lowering device 31 is operated to lower the raising mast 30 to a horizontal state around the raising/lowering shaft 29 (see the two-dot chain line in FIG. 3), and the lifting cup 21 and the shielding door 2 are then lowered.
2 and 2 upward to open the hatch 20 and transport the transport trolley 2.
7 is transferred from the hatch 20 to the fuel handling building 18 side by the travel guide rail 26 and stopped above the storage booth 16. Then, the mast raising/lowering device 31 is operated again to raise the raising/lowering mast 30 vertically around the raising/lowering shaft 29, and in this state, the hoisting device 34 is activated to raise the raising/lowering mast 30.
The fuel assembly 15 inside is suspended and put into the storage booth 16.
新たな燃料集合体１５を炉心１３内へ搬入する場合には
、この状態で新たな燃料集合体１５をグリッパ３６に把
持させ、上述した手順の逆の手順で移送台車２７を格納
容器１１側へ搬送すれば良い。When carrying a new fuel assembly 15 into the reactor core 13, the new fuel assembly 15 is gripped by the gripper 36 in this state, and the transfer cart 27 is moved toward the containment vessel 11 in the reverse order of the above-mentioned procedure. All you have to do is transport it.
〈発明の効果〉
本発明の原子炉用核燃料移送設備によると、格納容器と
燃料取扱建屋との間を往復動する移送台車をキャビティ
及びビットの上方に配置し、更に燃料集合体を収納し得
る起倒マストを移送台車に対して起倒自在に取付けたの
で、クレーン設備を従来のように二つ配置する必要がな
く、コストの削減が可能である。<Effects of the Invention> According to the nuclear fuel transfer equipment for a nuclear reactor of the present invention, a transfer cart that reciprocates between the containment vessel and the fuel handling building is disposed above the cavity and the bit, and can further accommodate the fuel assembly. Since the collapsible mast is attached to the transfer carriage so that it can be tilted and tilted, there is no need to arrange two crane facilities as in the conventional system, and costs can be reduced.
又、このクレーン設備がキャビティやビットの冷却水中
になく、空中に設けられていることから冷却水の水抜き
を行わなくても良く、保守点検作業を迅速且つ容易に行
うことができろ。更に、起倒マストを横倒しの状態で格
納容器と燃料取扱建屋との界壁を通過させろようにした
ので、ハツチの通路断面積を小さくすることが可能であ
り、安全性が高い。Furthermore, since this crane equipment is not in the cooling water of the cavity or bit, but is installed in the air, there is no need to drain the cooling water, and maintenance and inspection work can be performed quickly and easily. Furthermore, since the mast is allowed to pass through the boundary wall between the containment vessel and the fuel handling building in a sideways state, it is possible to reduce the cross-sectional area of the hatch passage, resulting in high safety.
第１図は本発明による原子炉用核燃料移送設備の一実施
例の概念図、第２図はその■−■矢視断面図、第３図は
その右側面図、第４図は従来の原子炉用核燃料移送設備
の一例を表す概念図である。
又、図中の符号で１１は格納容器、１２は遮蔽体、１３
は炉心、１４は原子炉容器、１５は燃料集会体、１７は
ビット、１８は燃料取扱建屋、１９はキャビティ、２０
はハツチ、２１は吊上げ蓋、２２は遮蔽扉、２６は走行
案内レール、２７は移送台車、２８はサドル、２９は起
倒軸、３０は起倒マスト、３１はマスト起倒装置、３２
．３３は伸縮マスト、３４は巻上げ装置、３５はワイヤ
、３６はグリッパ、３７は開閉蓋、３８は蓋開閉装置で
ある。
特 許 出 願 人
三菱重工業株式会社
日本原子力発電株式会社
代 理 人Fig. 1 is a conceptual diagram of an embodiment of nuclear fuel transfer equipment for a nuclear reactor according to the present invention, Fig. 2 is a cross-sectional view taken along the ■-■ arrow, Fig. 3 is a right side view thereof, and Fig. 4 is a conventional nuclear fuel transfer facility. FIG. 2 is a conceptual diagram showing an example of nuclear fuel transfer equipment for a reactor. Also, in the figures, 11 is a containment vessel, 12 is a shield, and 13 is a
is the reactor core, 14 is the reactor vessel, 15 is the fuel assembly, 17 is the bit, 18 is the fuel handling building, 19 is the cavity, 20
is a hatch, 21 is a lifting lid, 22 is a shielding door, 26 is a traveling guide rail, 27 is a transfer trolley, 28 is a saddle, 29 is a lifting shaft, 30 is a lifting mast, 31 is a mast lifting device, 32
．． 33 is a telescopic mast, 34 is a hoisting device, 35 is a wire, 36 is a gripper, 37 is an opening/closing lid, and 38 is a lid opening/closing device. Patent applicant Mitsubishi Heavy Industries, Ltd. Japan Atomic Power Co., Ltd. Agent
Claims (1)
れた格納容器と、この格納容器に隣接して設置され且つ
燃料ラックを収納すると共にビット内に冷却水が貯留さ
れた燃料取扱建屋と、前記キャビティ及び前記ビット上
方に敷設されて前記格納容器と前記燃料取扱建屋とに連
通する走行案内レールと、この走行案内レールに沿って
前記格納容器と前記燃料取扱建屋との間を往復駆動する
移送台車と、この移送台車に対して水平な旋回軸回りに
起倒自在に枢支された起倒マストと、先端に燃料集合体
を把持し得るグリッパが装着され且つ前記起倒マストに
対し伸縮自在に取付けられて前記燃料集合体と共に前記
起倒マスト内に引き込まれる伸縮マストを具えた原子炉
用核燃料移送設備。a containment vessel that houses a nuclear reactor and has cooling water stored in a cavity; a fuel handling building installed adjacent to the containment vessel that houses a fuel rack and has cooling water stored in a bit; a traveling guide rail laid above the cavity and the bit and communicating with the containment vessel and the fuel handling building; and a transfer trolley that reciprocates between the containing vessel and the fuel handling building along the traveling guide rail. and a tilting mast that is pivotably supported around a pivot axis horizontal to the transfer cart, and a gripper that can grip the fuel assembly is attached to the tip and is extendable and retractable with respect to the tilting mast. A nuclear fuel transfer facility for a nuclear reactor, comprising a telescoping mast that is attached and retracted into the folding mast together with the fuel assembly.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1028750A JPH02208599A (en) | 1989-02-09 | 1989-02-09 | Nuclear fuel transfer facility for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1028750A JPH02208599A (en) | 1989-02-09 | 1989-02-09 | Nuclear fuel transfer facility for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH02208599A true JPH02208599A (en) | 1990-08-20 |
Family
ID=12257085
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1028750A Pending JPH02208599A (en) | 1989-02-09 | 1989-02-09 | Nuclear fuel transfer facility for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH02208599A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0743652A1 (en) * | 1995-05-17 | 1996-11-20 | Reel S.A. | Method and installation for handling nuclear fuel assemblies within a reactor core |
| JP2011089929A (en) * | 2009-10-23 | 2011-05-06 | Toshiba Corp | Apparatus and method for piping work in nuclear reactor |
| EP2509079A3 (en) * | 2011-04-07 | 2014-12-31 | AREVA GmbH | Traverse for a lifting system, lifting system in a nuclear facility and operating method for a nuclear facility using such a traverse |
| CN108811286A (en) * | 2018-07-05 | 2018-11-13 | 中国工程物理研究院流体物理研究所 | A kind of overturning platform and its method for turning suitable for linear induction accelerator cavity |
| GB2588842A (en) * | 2020-07-23 | 2021-05-12 | Rolls Royce Plc | Nuclear refuelling device |
-
1989
- 1989-02-09 JP JP1028750A patent/JPH02208599A/en active Pending
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0743652A1 (en) * | 1995-05-17 | 1996-11-20 | Reel S.A. | Method and installation for handling nuclear fuel assemblies within a reactor core |
| FR2734391A1 (en) * | 1995-05-17 | 1996-11-22 | Reel Sa | METHOD AND DEVICE FOR HANDLING NUCLEAR FUEL ASSEMBLIES WITHIN A REACTOR CORE |
| JP2011089929A (en) * | 2009-10-23 | 2011-05-06 | Toshiba Corp | Apparatus and method for piping work in nuclear reactor |
| EP2509079A3 (en) * | 2011-04-07 | 2014-12-31 | AREVA GmbH | Traverse for a lifting system, lifting system in a nuclear facility and operating method for a nuclear facility using such a traverse |
| CN108811286A (en) * | 2018-07-05 | 2018-11-13 | 中国工程物理研究院流体物理研究所 | A kind of overturning platform and its method for turning suitable for linear induction accelerator cavity |
| CN108811286B (en) * | 2018-07-05 | 2020-03-31 | 中国工程物理研究院流体物理研究所 | Overturning platform suitable for linear induction accelerator cavity and overturning method thereof |
| GB2588842A (en) * | 2020-07-23 | 2021-05-12 | Rolls Royce Plc | Nuclear refuelling device |
| WO2022017880A1 (en) * | 2020-07-23 | 2022-01-27 | Rolls-Royce Plc | Nuclear refuelling device |
| CN115885351A (en) * | 2020-07-23 | 2023-03-31 | 劳斯莱斯Smr有限公司 | nuclear refueling unit |
| US20230298775A1 (en) * | 2020-07-23 | 2023-09-21 | Rolls-Royce Plc | Nuclear refuelling device |
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