JPH02285293A - Reactor sodium injection type sodium canning method and can handling assembly - Google Patents

Reactor sodium injection type sodium canning method and can handling assembly

Info

Publication number
JPH02285293A
JPH02285293A JP1108016A JP10801689A JPH02285293A JP H02285293 A JPH02285293 A JP H02285293A JP 1108016 A JP1108016 A JP 1108016A JP 10801689 A JP10801689 A JP 10801689A JP H02285293 A JPH02285293 A JP H02285293A
Authority
JP
Japan
Prior art keywords
sodium
fuel
boot
assembly
reactor
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
Application number
JP1108016A
Other languages
Japanese (ja)
Other versions
JP2658385B2 (en
Inventor
Masato Kinoshita
木下　誠人
Kazuhiko Nitta
新田　和彦
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.)
Fuji Electric Co Ltd
Original Assignee
Fuji Electric Co 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 Fuji Electric Co Ltd filed Critical Fuji Electric Co Ltd
Priority to JP1108016A priority Critical patent/JP2658385B2/en
Publication of JPH02285293A publication Critical patent/JPH02285293A/en
Application granted granted Critical
Publication of JP2658385B2 publication Critical patent/JP2658385B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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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

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  • Fuel Cell (AREA)

Abstract

PURPOSE:To allow the assembly not to need a special purpose sodium injection system and the like by providing the aggregate with a can shell for housing a fuel assembly and a boot for keeping airtightness with the outer peripheral face of the can shell to house the can shell and constituting the can shell and the boot so that they can be disassemblable. CONSTITUTION:A can handling assembly 25 is composed of a can shell 3 for housing a fuel assembly 7, a boot 1 for housing the can shell 3, a siphon tube 5 for covering the upper parts of the can shell 3 and the boot 1 to detachably mount on the boot 1 so as to regulate sodium 8 in the can shell 3, a siphon element 4 having a handling head 6 for engaging with a gripper 22 and a seal 2 sandwiching between the upper end of the can shell 3 and the boot 1 and the inside of the element 4. When the aggregate 25 is pulled up from a reactor with the use of a fuel taken-in and out machine, the sodium 8 is exhausted from the siphon tube 5. The handling of the assembly 25 in an argon gas cell is allowed to insert the gripper from the head 6 of the element 4 to allow it to easily lock with the fuel assembly 7 so as to move.

Description

【発明の詳細な説明】[Detailed description of the invention]

（産業上の利用分野］ この発明は、高速増殖炉の使用済燃料を冷却媒体ととも
に貯蔵、保管するための缶詰方法及びこれらの燃料を収
容して移送するための缶取扱用集合体の構造に関する。(Industrial Application Field) This invention relates to a canning method for storing and storing spent fuel of a fast breeder reactor together with a cooling medium, and a structure of a can handling assembly for storing and transporting these fuels. .

【従来の技術】[Conventional technology]

高速増殖炉は減速材を用いず、冷却材にナトリウムを用
い、原子炉容器内のナトリウム液面上はアルゴンガスで
満たされている。原子炉容器内のラックトロからキャス
ク内容器に数本ずつ収容さ料貯蔵ラックが並べられてい
る。 第５図は高速増殖炉の燃料取扱装置の配置図である。使
用済燃料は燃料交換機９により炉心から取り出され、炉
内燃料貯蔵ラックに貯蔵して崩壊熱レベルを低下させた
後、原子炉容器２６から燃料出入機１０によって外部へ
取り出し、炉外中継槽１１を経て、取り出された使用済
燃料は、付着ナトリウムの反応を防ぐため不活性のアル
ゴンガスが満たされたアルゴンガスセル２４内をインセ
ルクレーン１２によりセル床下に設けられた固定式の燃
料洗浄槽１３に受は渡されて洗浄される。 洗浄が完了した使用済燃料は、地下台車１４に移され、
さらに水プール室燃料移送機１５によって水をプールし
た使用済燃料貯蔵ラック１６内に移送され、再処理工場
へ搬出されるまで貯蔵される。 また、使用済燃料の再処理工場への搬出手順は、水プー
ル室燃料移送機１５により使用済燃料貯蔵れた後、キャ
スク蓋取扱クレーン１７を用いてキャスク接続装置１８
を経てキャスク台車１９に受は渡され、天井クレーン２
０により吊り上げられ港湾設備まで運ばれる。高発熱燃
料及び破損燃料は缶詰装置２１に移送し、缶詰専用に備
えたナトリウム注入系あるいは水注入系により缶詰缶内
にナトリウムあるいは水を注入した後に缶詰缶に蓋をし
て貯蔵保管していた。Fast breeder reactors do not use moderators, use sodium as a coolant, and the area above the sodium liquid level in the reactor vessel is filled with argon gas. Several storage racks are lined up inside the reactor vessel, each containing several racks stored in the cask container. FIG. 5 is a layout diagram of the fuel handling equipment of the fast breeder reactor. The spent fuel is taken out from the core by the fuel exchange machine 9 and stored in the in-core fuel storage rack to reduce the decay heat level, and then taken out from the reactor vessel 26 by the fuel inlet/output machine 10 and transferred to the out-of-core relay tank 11. After that, the spent fuel is transported by an in-cell crane 12 through an argon gas cell 24 filled with inert argon gas to prevent reaction of adhering sodium to a fixed fuel cleaning tank 13 installed under the cell floor. The uke is handed over and washed. The spent fuel that has been cleaned is transferred to the underground truck 14,
Further, the spent fuel is transferred by the water pool chamber fuel transfer device 15 into the spent fuel storage rack 16 in which water is pooled, and is stored until it is transported to the reprocessing plant. In addition, the procedure for transporting spent fuel to the reprocessing plant is that after the spent fuel is stored by the water pool room fuel transfer device 15, the cask lid handling crane 17 is used to transport the spent fuel to the cask connecting device 18.
After that, the receiver is transferred to the cask truck 19, and then the overhead crane 2
0 and transported to port facilities. High heat generating fuel and damaged fuel were transferred to the canning device 21, and after injecting sodium or water into the cans using a sodium injection system or water injection system provided exclusively for canning, the cans were covered and stored. .

【発明が解決しようとする課題】[Problem to be solved by the invention]

上記従来技術によれば、使用済燃料をナトリウムに漬け
て缶詰にするとき、原子炉容器外に設けた缶詰装置にて
缶詰内にナトリウムを注入するため、専用のナトリウム
注入系とナトリウム浄化系が必要となる。 また原子炉容器内で缶詰缶を浸漬し、缶詰缶にナトリウ
ムを注入する方法では、缶詰缶外面に原子炉容器内で付
着したナトリウムにより缶詰缶移送中の放射化したナト
リウムの飛散により、汚染が拡散するという問題があっ
た。 この発明は、缶詰缶外面にナトリウムが付着しないよう
にし、かつ缶詰装置における使用済燃料取扱のために、
専用のナトリウム注入系とナトリウム浄化系を必要とし
ないナトリウム缶詰方法及びこの缶詰方法に用いる缶取
扱用集合体を提供することを目的とする。According to the above conventional technology, when spent fuel is soaked in sodium and canned, sodium is injected into the can using a canning device installed outside the reactor vessel, so a dedicated sodium injection system and a sodium purification system are required. It becomes necessary. In addition, in the method of immersing cans in the reactor vessel and injecting sodium into the cans, the sodium adhering to the outside of the cans inside the reactor vessel can cause contamination due to the scattering of radioactive sodium during can transport. There was a problem with the spread. This invention prevents sodium from adhering to the outer surface of canned cans and handles spent fuel in canning equipment.
It is an object of the present invention to provide a sodium canning method that does not require a dedicated sodium injection system and a sodium purification system, and a can handling assembly used in this canning method.

【課題を解決するための手段】[Means to solve the problem]

上記目的は、炉外のアルゴンガスセル内に缶詰装置を有
する高速増殖炉の燃料取扱装置により使用済燃料をナト
リウムに漬けて缶詰にする方法において、燃料集合体を
収納する缶胴と、この缶胴の外周面と気密を保って前記
缶胴を収容するブーツとを備え、かつ前記缶胴と前記ブ
ーツとを分解。 組立自在に構成された缶取扱用集合体を用いて、この缶
取扱用集合体に前記原子炉内で前記使用済燃料を収容す
るとともに、ナトリウムを注入し、この缶取扱用集合体
を前記原子炉から前記缶詰装置まで移送し、前記缶詰装
置内で前記缶胴の上部に缶蓋をして前記使用済燃料を缶
胴内に缶詰にするようにした炉内ナトリウム注入型ナト
リウム缶詰方法によって達成される。 さらに、炉外のアルゴンガスセル内に缶詰装置を有する
高速増殖炉の燃料取扱装置により使用済燃料をナトリウ
ムに漬けて缶詰にする装置において、燃料集合体を収容
する缶胴と、この缶胴を収容するブーツと、前記缶胴及
びブーツの上部を覆い前記ブーツに着脱自在に係合し、
前記缶胴内のナトリウムの液位を調整するサイフオン管
とグリッパと噛み合うハンドリングヘッドとを有するサ
イフオンエレメントと、前記缶胴及びブーツの上端と前
記サイフオンエレメントの内側との間に挟んだシールと
から構成する缶取扱用集合体を用いれば好適である。 ｒ作　用】 使用済燃料をナトリウム缶詰にするときは、これらの燃
料を収納した缶胴を気密にブーツに保管するとともに、
分解１組立自在の缶詰取扱用集合体を用いて、原子炉内
で燃料とナトリウムとを缶胴内に収納してから缶詰装置
まで移送するようにしたので、缶詰装置においてナトリ
ウムを缶胴へ注入する必要がない。 また、缶詰装置において缶取扱用集合体を分解して使用
済燃料及び缶胴を取り出せば、缶胴の外表面はナトリウ
ムの付着がないので、缶胴に缶蓋をして移送中にナトリ
ウムによる放射能汚染はない。 缶取扱用集合体は、燃料集合体を収容する缶胴と、この
缶胴を収容するブーツと、前記缶胴及びブーツの上部を
覆い前記ブーツに着脱自在に係合し、前記缶胴内のナト
リウムの液位を調整するサイフオン管とグリッパに噛み
合うハンドリングヘッドとを有するサイフオンエレメン
トと、前記缶胴及びブーツの上端と前記サイフオンエレ
メントの内側との間に配置されるシールとから構成する
ので、缶胴の外表面とブーツ内面との間は気密に保たれ
、缶胴の外表面にはナトリウムの付着がない。The above purpose is to provide a can body for storing fuel assemblies and a can body for storing fuel assemblies in a method of canning spent fuel by soaking it in sodium using a fast breeder reactor fuel handling device that has a canning device in an argon gas cell outside the reactor. and a boot for accommodating the can body in an airtight manner with respect to the outer peripheral surface of the can body, and the can body and the boot can be disassembled. Using a can handling assembly configured to be freely assembled, the spent fuel is stored in the can handling assembly in the nuclear reactor, sodium is injected, and the can handling assembly is placed inside the nuclear reactor. Achieved by an in-furnace sodium injection type sodium canning method, in which the spent fuel is transferred from a furnace to the canning device, a can lid is placed on the top of the can body in the canning device, and the spent fuel is canned in the can body. be done. Furthermore, in a device for soaking spent fuel in sodium and canning it using the fuel handling equipment of a fast breeder reactor, which has a canning device in an argon gas cell outside the reactor, a can body that houses the fuel assembly and a can body that houses this can body are used. a boot that covers the can body and the upper part of the boot and removably engages with the boot;
a siphon element having a siphon tube that adjusts the liquid level of sodium in the can body and a handling head that engages with a gripper; a seal sandwiched between the upper ends of the can body and boot and the inside of the siphon element; It is preferable to use a can handling assembly consisting of: r Effect] When sodium canning spent fuel, store the can body containing the fuel airtight in a boot, and
Disassembly 1 Using a can handling assembly that can be assembled freely, fuel and sodium are stored in the can body inside the reactor and then transferred to the canning equipment, so that sodium can be injected into the can body in the canning equipment. There's no need to. In addition, if the can handling assembly is disassembled in the canning equipment and the spent fuel and can bodies are taken out, the outer surface of the can bodies will not have any sodium adhesion, so it is possible to cover the can bodies with can lids and prevent sodium buildup during transportation. There is no radioactive contamination. The can handling assembly includes a can body for accommodating the fuel assembly, a boot for accommodating the can body, a can body that covers the upper part of the can body and the boot, and is removably engaged with the boot. The siphon element comprises a siphon element having a siphon tube for adjusting the sodium liquid level and a handling head that engages with the gripper, and a seal disposed between the upper ends of the can body and boot and the inside of the siphon element. The space between the outer surface of the can body and the inner surface of the boot is kept airtight, and there is no adhesion of sodium to the outer surface of the can body.

【実施例】【Example】

以下図面に基づいてこの発明の詳細な説明する。第１図
はこの発明の実施例による缶取扱用集合体に、高発熱使
用済燃料または破損燃料などの燃料集合体を収容し、ナ
トリウムを満たした状態を示す断面図、第２図は第１図
のＡ−Ａ断面図、第３図は原子炉から取り出しアルゴン
ガスセル内に移送されたこの発明の実施例による缶取扱
用集合体の断面図である。 第５図において、高速増殖炉内から使用済燃料を取り出
すときは、通常液体ナトリウムを満たしたポットに燃料
集合体７を入れて燃料交換機９及び燃料出入機１０を用
いてアルゴンガスセル２４へ移送される。 しかし、この発明の実施例によれば、高発熱使用済燃料
あるいは破損燃料は、これらの燃料を収納する缶胴３と
、この缶胴３の外周面と気密を保って缶胴３を収容する
ブーツ１とを備え、かつ缶）胴３とブーツ１とを分解９
組立自在に構成された缶取扱用集合体２５を用いて、燃
料交換機１０により燃料集合体７を缶胴３に収容する。 さらに燃料集合体７及びナトリウム８を収容した缶取扱
用集合体２５のハンドリングヘッド６を燃料交換機９の
グリッパ２２を介して係合させ、燃料出入機１０及びイ
ンセルクレーン１２によりアルゴンガスセル２４内の缶
詰装置２１に移送し、サイフオンエレメント４とブーツ
ｌとを取り出し缶′ｊＩＬ２３で蓋をして燃料集合体７
を密封した後、使用済燃料貯蔵ラック１６に保管する。 この発明の実施例による缶取扱用集合体２５は、燃料集
合体７を収容する缶胴３と、缶Ｗ４３を収容するブーツ
１と、缶胴３及びブーツｌの上部を覆いブーツ１に着脱
自在に係合し、缶胴３内のナトリウム８の液位を調整す
るサイフオン管５とグリッパ２２に噛み合うハンドリン
グヘッド６とを有するサイフオンエレメント４と、缶胴
３及ヒフ’−ツ１の上端とサイフオンエレメント４の内
側との間に挟んだシール２とから構成され、このシール
２を圧縮しているので、缶胴３の外周面とブーツ１の内
面との間は気密となる。そのため、原子炉２６内に缶取
扱用集合体２５を浸漬しても、缶胴３の外面に液体ナト
リウムが付着することはない。 なお、ブーツ１の上部外面にねじを備え、サイフオンエ
レメント４の内面にスプライン溝を刻んで係合させ、サ
イフオンエレメント４を回転させてシール２を圧縮する
。 燃料出入機１０により原子炉２６から缶取扱用集合体２
５が引き上げられると、途中の原子炉液面部にて、サイ
フオンエレメント４に備えたサイフオン管５から缶胴３
内の液体ナトリウム８が排出され、燃料集合体７のグリ
ップ部が液体ナトリウム８液面より露出する。この状態
を第３図に示す。 アルゴンガスセル２４内での缶取扱用集合体２５の取扱
は、サイフオンエレメント４のハンドリングへラド６か
らグリッパを挿入して燃料集合体７に容易に係合させ、
移送できる０缶詰装置２１に移送された缶取扱用集合体
２５は、サイフォンエ缶胴３上部の開口に缶！！２３を
ボルト締めにより取り付は燃料集合体７を密封する。第
４図は、第３図の缶胴３に缶蓋２３を取り付けた状態を
示す図である。The present invention will be described in detail below based on the drawings. FIG. 1 is a sectional view showing a state in which a can handling assembly according to an embodiment of the present invention accommodates fuel assemblies such as high heat generation spent fuel or damaged fuel and is filled with sodium. 3 is a cross-sectional view of a can handling assembly according to an embodiment of the present invention taken out from a nuclear reactor and transferred into an argon gas cell. In FIG. 5, when taking out spent fuel from inside a fast breeder reactor, a fuel assembly 7 is usually placed in a pot filled with liquid sodium and transferred to an argon gas cell 24 using a fuel exchanger 9 and a fuel inlet/outer 10. Ru. However, according to the embodiment of the present invention, high heat generation spent fuel or damaged fuel is stored in the can body 3 that accommodates these fuels, and the can body 3 is kept airtight with the outer peripheral surface of this can body 3. Disassemble the body 3 and the boots 1 9
The fuel assembly 7 is housed in the can body 3 by the fuel exchanger 10 using the can handling assembly 25 configured to be freely assembled. Further, the handling head 6 of the can handling assembly 25 containing the fuel assembly 7 and the sodium 8 is engaged via the gripper 22 of the fuel exchanger 9, and the canister in the argon gas cell 24 is moved by the fuel loading/unloading machine 10 and the in-cell crane 12. Transfer it to the device 21, take out the siphon element 4 and the boot l, cover it with a can 'jIL23, and remove the fuel assembly 7.
After sealing, the spent fuel is stored in the spent fuel storage rack 16. The can handling assembly 25 according to the embodiment of the present invention includes a can body 3 that accommodates the fuel assembly 7, a boot 1 that accommodates the can W43, and covers the upper parts of the can body 3 and the boot l, and is detachably attached to the boot 1. A siphon element 4 having a siphon tube 5 that engages with the can body 3 to adjust the liquid level of the sodium 8 in the can body 3 and a handling head 6 that engages with the gripper 22; The seal 2 is sandwiched between the inside of the siphon element 4 and the seal 2 is compressed, so that the space between the outer circumferential surface of the can body 3 and the inner surface of the boot 1 becomes airtight. Therefore, even if the can handling assembly 25 is immersed in the nuclear reactor 26, liquid sodium will not adhere to the outer surface of the can body 3. A screw is provided on the outer surface of the upper part of the boot 1, and a spline groove is cut into the inner surface of the siphon-on element 4 so as to be engaged therewith, and the seal 2 is compressed by rotating the siphon-on element 4. The can handling assembly 2 is transferred from the reactor 26 by the fuel inlet/output machine 10.
5 is pulled up, the can body 3 is removed from the siphon tube 5 provided in the siphon element 4 at the reactor liquid level midway.
The liquid sodium 8 inside is discharged, and the grip portion of the fuel assembly 7 is exposed from the surface of the liquid sodium 8. This state is shown in FIG. The can handling assembly 25 is handled within the argon gas cell 24 by inserting a gripper from the rad 6 into the handling handle of the siphon element 4 and easily engaging the fuel assembly 7.
The can handling assembly 25 transferred to the canning device 21 is placed into the opening at the top of the siphon can body 3. ! 23 is attached by bolting to seal the fuel assembly 7. FIG. 4 is a diagram showing a state in which the can lid 23 is attached to the can body 3 of FIG. 3.

【発明の効果】【Effect of the invention】

この発明によれば、燃料集合体を収納する缶胴と、この
缶胴の外周面と気密を保って前記缶胴を収納するブーツ
とを備え、かつ前記缶胴と前記ブーツとを分解９組立自
在に構成された缶取扱用集合体を用いて、この缶取扱用
集合体に原子炉内で使用済燃料とナトリウムとを収容し
、この缶取扱用集合体を前記原子炉から缶詰装置まで移
送し、前記缶詰装置内で缶胴の上部に缶蓋をして前記燃
料を密封するようにしたので、缶胴内のナトリウムは原
子炉から供給されるため、アルゴンガスセル内の缶詰装
置には専用のナトリウム注入系及び浄化系を必要としな
い。また原子炉内で缶胴に使用済燃料を収容し、ナトリ
ウムを満たしても、缶胴の外面にナトリウムが付看する
ことがないので、缶詰め装置から使用済燃料を収納した
缶胴を取り出し外部へ移送すしてもナトリウムにより汚
染することはない。According to this invention, the can body is provided with a can body that stores a fuel assembly, and a boot that stores the can body while maintaining airtightness with the outer peripheral surface of the can body, and the can body and the boot are disassembled and reassembled. A freely configured can handling assembly is used to store spent fuel and sodium in the reactor, and the can handling assembly is transferred from the reactor to the canning equipment. However, since the can lid was placed on the top of the can body in the canning device to seal the fuel, the sodium in the can body was supplied from the nuclear reactor, so the canning device inside the argon gas cell had a special purpose. does not require additional sodium injection and purification systems. In addition, even if spent fuel is stored in a can body inside a nuclear reactor and the can body is filled with sodium, sodium will not stick to the outside surface of the can body, so the can body containing spent fuel can be removed from the canner and removed from the can body. There will be no sodium contamination even if the sample is transferred to

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

第１図はこの発明の実施例による缶取扱用集合体に燃料
集合体を収容しナトリウムを満たした状態を示す断面図
、第２図は第１図のＡ−Ａ断面図、第３図は原子炉から
取り出しアルゴンガスセル内に移送されたこの発明の実
施例による缶取扱用集合体の断面図、第４図は第３図の
缶胴に缶蓋を取り付けた状態を示す断面図、第５図は高
速増殖炉の燃料取扱装置の配置図である。 １：ブーツ、２：シール、３：缶胴、４：サイフオンエ
レメント、５：サイフオン管、６：ハンドリングヘッド
、７：燃料集合体、８：ナトリウム、９：燃料交換機、
１０：燃料出入機、２１：缶詰装置、２２ニゲリツパ、
２３：缶蓋、２４：アルゴンガスセル、２５：缶取扱用
集合体、２６：゛原子炉容器。 第 図 第 図FIG. 1 is a sectional view showing a fuel assembly accommodated in a can handling assembly according to an embodiment of the present invention and filled with sodium, FIG. 2 is a sectional view taken along line A-A in FIG. 1, and FIG. 4 is a sectional view of a can handling assembly according to an embodiment of the present invention taken out of a nuclear reactor and transferred to an argon gas cell; FIG. 4 is a sectional view showing a can lid attached to the can body of FIG. 3; FIG. The figure is a layout diagram of the fuel handling equipment of a fast breeder reactor. 1: Boot, 2: Seal, 3: Can body, 4: Siphon element, 5: Siphon tube, 6: Handling head, 7: Fuel assembly, 8: Sodium, 9: Fuel exchange machine,
10: Fuel loading/unloading machine, 21: Canning device, 22 Nigerippa,
23: can lid, 24: argon gas cell, 25: can handling assembly, 26: reactor vessel. Figure Figure

Claims (1)

【特許請求の範囲】 １）炉外のアルゴンガスセル内に缶詰装置を有する高速
増殖炉の燃料取扱装置により使用済燃料をナトリウムに
漬けて缶詰にする方法において、燃料集合体を収納する
缶胴と、この缶胴の外周面と気蜜を保って前記缶胴を収
容するブーツとを備え、かつ前記缶胴と前記ブーツとを
分解、組立自在に構成された缶取扱用集合体を用いて、
この缶取扱用集合体に前記原子炉内で前記使用済燃料を
収容するとともに、ナトリウムを注入し、この缶取扱用
集合体を前記原子炉から前記缶詰装置まで移送し、前記
缶詰装置内で前記缶胴の上部に缶蓋をして前記使用済燃
料を缶胴内に缶詰にするようにしたことを特徴とする炉
内ナトリウム注入型ナトリウム缶詰方法。 ２）炉外のアルゴンガスセル内に缶詰装置を有する高速
増殖炉の燃料取扱装置により使用済燃料をナトウムに漬
けて缶詰にする装置において、燃料集合体を収容する缶
胴と、この缶胴を収容するブーツと、前記缶胴及びブー
ツの上部を覆い前記ブーツに着脱自在に係合し、前記缶
胴内のナトリウムの液位を調整するサイフオン管とグリ
ッパと噛み合うハンドリングヘッドとを有するサイフォ
ンエレメントと、前記缶胴及びブーツの上端と前記サイ
フォンエレメントの内側との間に挟んだシールとから構
成することを特徴とする缶取扱用集合体。[Claims] 1) In a method for soaking spent fuel in sodium and canning it using a fast breeder reactor fuel handling device having a canning device in an argon gas cell outside the reactor, a can body for storing a fuel assembly; , using a can handling assembly comprising a boot for accommodating the can body while maintaining airtightness with the outer peripheral surface of the can body, and configured such that the can body and the boot can be disassembled and assembled,
The spent fuel is stored in the can handling assembly in the reactor, and sodium is injected into the can handling assembly, and the can handling assembly is transferred from the reactor to the canner, and inside the canner, the spent fuel is injected into the canner. An in-furnace sodium injection type sodium canning method, characterized in that the spent fuel is canned in the can body by placing a can lid on the top of the can body. 2) In a fast breeder reactor fuel handling device that has a canning device in an argon gas cell outside the reactor, spent fuel is soaked in sodium and canned, including a can body that houses the fuel assembly and a can body that houses this can body. a siphon element having a handle head that covers the can body and the upper part of the boot and removably engages with the boot and engages with a siphon tube and a gripper that adjusts the liquid level of sodium in the can body; A can handling assembly comprising a seal sandwiched between the upper end of the can body and boot and the inside of the siphon element.
JP1108016A 1989-04-27 1989-04-27 Sodium canning type sodium canning method in furnace and assembly for can handling Expired - Lifetime JP2658385B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1108016A JP2658385B2 (en) 1989-04-27 1989-04-27 Sodium canning type sodium canning method in furnace and assembly for can handling

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1108016A JP2658385B2 (en) 1989-04-27 1989-04-27 Sodium canning type sodium canning method in furnace and assembly for can handling

Publications (2)

Publication Number Publication Date
JPH02285293A true JPH02285293A (en) 1990-11-22
JP2658385B2 JP2658385B2 (en) 1997-09-30

Family

ID=14473848

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1108016A Expired - Lifetime JP2658385B2 (en) 1989-04-27 1989-04-27 Sodium canning type sodium canning method in furnace and assembly for can handling

Country Status (1)

Country Link
JP (1) JP2658385B2 (en)

Also Published As

Publication number Publication date
JP2658385B2 (en) 1997-09-30

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