JPH04127087A - Liquid lithium control type fast breeder - Google Patents

Liquid lithium control type fast breeder

Info

Publication number
JPH04127087A
JPH04127087A JP2247173A JP24717390A JPH04127087A JP H04127087 A JPH04127087 A JP H04127087A JP 2247173 A JP2247173 A JP 2247173A JP 24717390 A JP24717390 A JP 24717390A JP H04127087 A JPH04127087 A JP H04127087A
Authority
JP
Japan
Prior art keywords
reactor
cylinder body
case
liquid lithium
core
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
JP2247173A
Other languages
Japanese (ja)
Inventor
Mineo Sekiguchi
関口 峰生
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP2247173A priority Critical patent/JPH04127087A/en
Publication of JPH04127087A publication Critical patent/JPH04127087A/en
Pending legal-status Critical Current

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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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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To achieve a simplification of a construction dispensing with a rotary plug by arranging a control body having an expandable closed cylinder body within a case parallel to a reactor core shaft in an outer circumferential area of a reactor core to connect a tank of liquid lithium to the closed cylinder body. CONSTITUTION:To control an output of a nuclear reactor, a pump 22 of a controller 13 is started to suck a coolant within a reactor vessel 2 from a piping 16 to flow into a lower space 23 in a case 17 through a piping 15. As a result, a pressure in the space 23 rises higher than that in a closed cylinder body 20 to compress a bellows joint 19 of the cylinder body 20 so that the cylinder body 20 is reduced in an axial direction thereof to achieve a balance between the pressure inside and outside the cylinder body. With the reduction of the cylinder body, a part of a liquid lithium 25 inside is extruded to be returned to a tank 21. A lower end of a liquid column of the liquid lithium 25 in the case 17 rises accordingly, a condition which is as noted when a control rod is pulled out in the reactor. When the pump 22 is stopped to open a valve 24, the cylinder body 20 stretches by a return force of the joint 19 of the cylinder body 20 and the coolant is extruded to be returned into the reactor vessel through the piping 15 or the like.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は液体リチウムを制御材とした液体金属ナトリウ
ム冷却型の高速増殖炉、特に原子炉上部機器を簡素化し
た液体リチウム制御式高速増殖炉に係る。
[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) The present invention relates to a liquid metal sodium cooled fast breeder reactor using liquid lithium as a control material, particularly a liquid lithium fast breeder reactor with simplified upper reactor equipment. Relating to controlled fast breeder reactors.

(従来の技術) 液体金属ナトリウム冷却型の高速増殖炉の原子炉上部構
造は、第3図に示すように炉心1を収容する原子炉容器
2の蓋3の偏心位置に設けた回転プラグ4と、この回転
プラグ上に設けた炉心上部機構5および燃料交換装W6
とよりなる。炉心上部機構5には制御体駆動機構7が含
まれ、制御体駆動機構7は炉心1に対する制御体の挿抜
を行い、原子炉の出力を制御するものである。燃料交換
に際しては回転プラグ4を回動させて炉心上部機構5を
炉心上方から移動させ、燃料交換装!!6を炉心1上方
位置にもたらして燃料の交換を行う。
(Prior Art) As shown in FIG. 3, the reactor upper structure of a liquid metal sodium-cooled fast breeder reactor consists of a rotary plug 4 and a rotary plug 4 provided at an eccentric position on a lid 3 of a reactor vessel 2 housing a reactor core 1. , core upper mechanism 5 and fuel exchange equipment W6 provided on this rotating plug.
It becomes more. The upper core mechanism 5 includes a control body drive mechanism 7, and the control body drive mechanism 7 inserts and removes a control body into the reactor core 1 and controls the output of the nuclear reactor. When exchanging fuel, the rotary plug 4 is rotated to move the upper core mechanism 5 from above the core, and the fuel exchange equipment is installed! ! 6 is brought to a position above the core 1 and the fuel is exchanged.

燃料交換装置6と炉心上部機構5を支持し回転する回転
プラグ4は、放射線遮蔽、断熱構造としであるため、被
支持物ともで数百トンの重量を有する。而して、この回
転プラグ4を回転駆動するために必要な多数の機器、設
備(歯車、駆動装置、軸受、回転部気密装置1回転部ケ
ーブル処理装置等)により、原子炉上部は極めて複雑な
構造となっており、設計、製作、据付、組立、試験、検
査等の面で多大の労力を必要としている。
The rotary plug 4 that supports and rotates the fuel exchange device 6 and the upper core mechanism 5 has a radiation shielding and heat insulating structure, and therefore weighs several hundred tons together with the supported objects. The upper part of the reactor is extremely complex due to the large number of devices and equipment (gears, drive devices, bearings, rotating part air sealing device 1 rotating part cable handling device, etc.) required to drive the rotating plug 4. The structure requires a great deal of effort in terms of design, manufacturing, installation, assembly, testing, inspection, etc.

なお、第3図中8は燃料交換装置6のアーム、9はこれ
に吊下支持された燃料、10は炉内構造物、11は前記
アーム8に設けられ燃料9を掴持するグリッパをそれぞ
れ示している。
In FIG. 3, 8 is an arm of the fuel exchange device 6, 9 is the fuel suspended and supported by this, 10 is a reactor internal structure, and 11 is a gripper provided on the arm 8 for gripping the fuel 9. It shows.

(発明が解決しようとする課題) 上記のように従来の原子炉上部構造にあっては、燃料交
換に際して炉心上部機構5を炉心1上方位置から避退さ
せ、燃料交換袋M6を炉心1上方にもたらし、これを各
燃料上方に移動させるために巨大な回転プラグ3を設け
ていた。また、この回転プラグ3はかなりの重量物であ
るにもかかわらず、燃料交換に際しての位置決めのため
高精度のものとする必要があった。
(Problems to be Solved by the Invention) As described above, in the conventional reactor upper structure, the core upper mechanism 5 is evacuated from a position above the reactor core 1 during fuel exchange, and the fuel exchange bag M6 is moved above the reactor core 1. A huge rotating plug 3 was provided to bring the fuel and move it above each fuel. Further, although the rotary plug 3 is quite heavy, it needs to be highly accurate for positioning during fuel exchange.

本発明は上記の事情に基づきなされたもので、上記のよ
うな問題を含む回転プラグを設けることなく、原子炉の
上部構造を簡素として設計、製作、据付等が容易であり
、しかも安価な原子炉容器蓋を具えた液体リチウム制御
式高速増殖炉を提供することを目的としている。
The present invention has been made based on the above-mentioned circumstances, and it is possible to simplify the upper structure of a nuclear reactor without providing a rotating plug that causes the above-mentioned problems. The object is to provide a liquid lithium controlled fast breeder reactor equipped with a reactor vessel lid.

[発明の構成] (課題を解決するための手段) 本発明の液体リチウム制御式高速増殖炉は、液体金属冷
却型高速増殖炉の炉心を収容する原子炉容器の固定蓋中
心を貫通して炉心の任意の部位に到達できる燃料交換装
置を設け、前記炉心外周領域には炉心軸に平行なケース
およびこのケース内に収容され炉心軸方向に伸縮可能な
密閉筒体を有する制御体を配置し、前記密閉筒体には液
体リチウムのタンクを接続し、前記ケースにはケース内
の圧力を前記原子炉容器内の冷却材の給排により調整す
る制御装置を接続したことを特徴とする。
[Structure of the Invention] (Means for Solving the Problems) A liquid lithium-controlled fast breeder reactor of the present invention penetrates the center of a fixed lid of a reactor vessel housing a core of a liquid metal cooled fast breeder reactor. a fuel exchange device that can reach any part of the reactor core, and a control body having a case parallel to the core axis and a closed cylindrical body housed in the case and expandable and retractable in the core axis direction is disposed in the outer peripheral region of the reactor core, A liquid lithium tank is connected to the sealed cylindrical body, and a control device is connected to the case to adjust the pressure inside the case by supplying and discharging coolant in the reactor vessel.

(作用) 上記構成の本発明液体リチウム制御式高速増殖炉におい
ては、前記制御装置により原子炉容器内の冷却材を吸引
し、これをケース内に注入する。
(Function) In the liquid lithium controlled fast breeder reactor of the present invention having the above configuration, the control device sucks the coolant in the reactor vessel and injects it into the case.

すると、ケース内の圧力が前記密閉筒体内のそれよりも
高くなる。ここで、密閉筒体がその軸方向に縮小するこ
とにより前記筒体内外の圧力のバランスがとられる。こ
れによって、密閉筒体内部にあった液体リチウムの一部
は押し出され、タンクに還流される。その分だけ前記ケ
ース内にある中性子吸収材、すなわち液体リチウムの液
柱下端が上昇されたこととなり、従来の原子炉において
制御棒が引き抜かれたのと同様の状態となる。
Then, the pressure inside the case becomes higher than that inside the sealed cylinder. Here, the pressure inside and outside the cylinder is balanced by shrinking the closed cylinder in its axial direction. As a result, some of the liquid lithium inside the sealed cylinder is pushed out and returned to the tank. The neutron absorber in the case, that is, the lower end of the liquid column of liquid lithium, is raised by that amount, resulting in a state similar to when a control rod is pulled out in a conventional nuclear reactor.

また、前記制御装置により前記ケース内の冷却材を排出
させれば、前記密閉筒体はその復元力により前記ケース
内に注入されていた冷却材は押し出され、原子炉容器内
に還流される。前記密閉筒体の伸張時にタンクからその
内部に液体リチウムが流入する。すなわち、前記ケース
内にある液体リチウムの液柱下端が下降されたこととな
り、従来の原子炉において制御棒が挿入されたのと同様
の状態となる。
Further, when the control device discharges the coolant in the case, the restoring force of the closed cylinder pushes out the coolant that has been injected into the case and flows back into the reactor vessel. When the closed cylinder is expanded, liquid lithium flows into it from the tank. That is, the lower end of the liquid column of liquid lithium in the case has been lowered, resulting in a state similar to when a control rod is inserted in a conventional nuclear reactor.

なお、前記ケース内の圧力は前記制御装置により任意に
設定することができ、これにより前記伸縮可能の密閉筒
体の軸方向寸法を任意に設定することができるから、従
来の制御体の炉心に対する挿抜と同様にして原子炉の出
力を制御することができる。
Note that the pressure inside the case can be set arbitrarily by the control device, and thereby the axial dimension of the expandable and retractable closed cylinder can be set arbitrarily, so that The output of the reactor can be controlled in the same way as insertion and removal.

(実施例) 第3図と同一部分には同一符号を付した第1図は本発明
一実施例の原子炉停止間の燃料交換時における縦断面図
、第2図はその要部の拡大断面図である。第1図におい
て、原子炉容器2の蓋3の中心部には燃料交換装置6が
設けられ、そのアーム8に設けたグリッパ11には燃料
9が吊下支持、されている。
(Example) The same parts as in Fig. 3 are given the same reference numerals. Fig. 1 is a longitudinal sectional view of one embodiment of the present invention during fuel exchange during reactor shutdown, and Fig. 2 is an enlarged sectional view of the main parts. It is a diagram. In FIG. 1, a fuel exchange device 6 is provided at the center of a lid 3 of a reactor vessel 2, and a fuel 9 is suspended and supported by a gripper 11 provided on an arm 8 of the fuel exchange device 6.

なお、炉心1の外周領域にはその詳細を第2図につき後
に説明する制御体12が装荷され、制御体12は同じく
第2図につき後に詳細を説明する制御器13と配管14
.15により接続されている。また、前記制御器13は
配管16により原子炉容器2内と連通されている。
A control body 12, the details of which will be explained later with reference to FIG.
.. 15. Further, the controller 13 is communicated with the inside of the reactor vessel 2 through a pipe 16.

以下第2図につき制御体12および制御器13の詳細を
説明する。制御体12は密閉円筒状のケース17を有し
、このケース内には大径部を上にして複数(図示は3)
箇の段付管18が次のよう↓こして収容されている。す
なわち、最上段の段付管はその大径端を前記ケース17
の上面壁に固着され、下位の段付管はその大径端間口縁
を上位の段付管の大径部下端外周とベローズ継手19に
よってそれぞれ連結されている。すなわち、*敷部の段
付管18はそれ等の個々が伸縮可能なベローズ継手19
で連結され、軸方向に伸縮可能な1箇の密閉筒体20を
形成している。
The details of the control body 12 and the controller 13 will be explained below with reference to FIG. The control body 12 has a closed cylindrical case 17, and inside this case there are a plurality of (three in the figure) with the large diameter part facing upward.
The stepped pipes 18 are housed in the following manner. That is, the uppermost stepped tube has its large diameter end connected to the case 17.
The lower stepped tube is fixed to the upper surface wall, and its large diameter end-to-end mouth edges are connected to the outer periphery of the large diameter lower end of the upper stepped tube by bellows joints 19, respectively. In other words, *The stepped pipes 18 in the bed section are individually expandable and retractable bellows joints 19.
are connected to form one closed cylinder 20 that is expandable and retractable in the axial direction.

配管14は制御器13内の上部に設けた液体リチウムの
タンク21底部と前記段付管18の最上段のものとを連
通させ、前記制御器13内の下部に設けられたポンプ2
2はその吸引口を配管16により原子炉容器2内に連通
させ、その吐出口は配管工5によって前記ケース17内
の下部空間23と連通されている。なお、上記リチウム
を収容するタンク21は不活性ガスによって加圧されて
いる。図中24は配管16と配管工5との間に設けた弁
を示している。
The piping 14 communicates the bottom of the liquid lithium tank 21 provided in the upper part of the controller 13 with the uppermost part of the stepped pipe 18, and connects the pump 2 provided in the lower part of the controller 13 with the bottom part of the liquid lithium tank 21 provided in the upper part of the controller 13.
2 has its suction port communicated with the inside of the reactor vessel 2 through a pipe 16, and its discharge port is communicated with a lower space 23 in the case 17 by a plumber 5. Note that the tank 21 containing the lithium is pressurized with an inert gas. In the figure, 24 indicates a valve provided between the pipe 16 and the plumber 5.

上記構成の本発明の液体リチウム制御式高速増殖炉は次
のように作動する。原子炉運転時には燃料交換装置6は
当然非作動とされ、燃料9は炉心1に所定の如く装荷さ
れている。
The liquid lithium controlled fast breeder reactor of the present invention having the above configuration operates as follows. During reactor operation, the fuel exchange device 6 is naturally inactive, and the fuel 9 is loaded into the reactor core 1 in a predetermined manner.

前記タンク21.配管14、伸縮可能な密閉筒体20内
には液体リチウム25が充たされている。
Said tank 21. The piping 14 and the expandable and retractable sealed cylinder 20 are filled with liquid lithium 25.

また、タンク21、配管14、密閉筒体20等はステン
レス鋼により構成さ九、それ等の液体リチウムと接する
面にはモリブデン等のコーティングを施しである。
Further, the tank 21, piping 14, sealed cylinder 20, etc. are made of stainless steel, and their surfaces that come into contact with liquid lithium are coated with molybdenum or the like.

ここで、原子炉の出力を制御するには制御器13のポン
プ22、弁24を使用する。ポンプ22を起動し原子炉
容器2内の冷却材を配管16から吸引し、配管15を介
してケース17内の下部空間23に注入する。すると、
前記下部空間23内の圧力が前記密閉筒体20内のそれ
よりも高くなる。ここで、密閉筒体20のベローズ継手
19は押し縮められ、密閉筒体20がその軸方向に縮小
することにより前記筒体内外の圧力のバランスがとられ
る。この密閉筒体20の縮小により、その内部にあった
液体リチウムの一部は押し呂され。
Here, the pump 22 and valve 24 of the controller 13 are used to control the output of the nuclear reactor. The pump 22 is started to suck the coolant in the reactor vessel 2 through the pipe 16 and inject it into the lower space 23 in the case 17 via the pipe 15. Then,
The pressure within the lower space 23 becomes higher than that within the sealed cylinder 20. Here, the bellows joint 19 of the closed cylinder 20 is compressed, and the closed cylinder 20 contracts in its axial direction, thereby balancing the pressure inside and outside the cylinder. Due to the shrinkage of the sealed cylinder 20, a portion of the liquid lithium inside the cylinder is pushed out.

タンク21に還流される。その分だけケース17内にあ
る中性子吸収材、すなわち液体リチウム25の液柱下端
が上昇されたこととなり、従来の原子炉において制御棒
が引き抜かれたのと同様の状態となる。
It is refluxed to the tank 21. The lower end of the liquid column of the neutron absorbing material in the case 17, that is, the liquid lithium 25, is raised by that amount, resulting in a state similar to when a control rod is pulled out in a conventional nuclear reactor.

また、前記ポンプ22を停止させ弁24を開けば、前記
密閉筒体20のベローズ継手19の復元力により密閉筒
体20は伸張し、これにより前記下部空間23内に注入
されていた冷却材は押し出され、配管15、弁24.配
管16を介して原子炉容器2内に還流される。これによ
り、前記下部空間23の圧力は下降させられる。また、
前記密閉筒体20の伸張時にタンク21から密閉筒体2
0内に液体リチウムが流入する。すなわち、ケース17
内にある液体リチウムの液柱下端が下降されたこととな
り、従来の原子炉において制御棒が挿入されたのと同様
の状態となる。
Furthermore, when the pump 22 is stopped and the valve 24 is opened, the hermetic cylinder 20 expands due to the restoring force of the bellows joint 19 of the hermetic cylinder 20, and as a result, the coolant injected into the lower space 23 is discharged. Extruded, piping 15, valve 24. It is refluxed into the reactor vessel 2 via the pipe 16. As a result, the pressure in the lower space 23 is lowered. Also,
When the sealed cylinder 20 is expanded, the sealed cylinder 2 is removed from the tank 21.
Liquid lithium flows into 0. That is, case 17
The lower end of the liquid lithium column inside the reactor has been lowered, similar to when a control rod is inserted in a conventional nuclear reactor.

なお、前記下部空間23の圧力は前記ポンプ22の回転
数、前記弁24の開度により任意に設定することができ
、これにより前記伸縮可能の密閉筒体20の軸方向寸法
を任意に設定することができるから、従来の制御棒の炉
心に対する挿抜と同様にして原子炉の出力を制御するこ
とができる。
Note that the pressure in the lower space 23 can be arbitrarily set by the rotation speed of the pump 22 and the opening degree of the valve 24, and thereby the axial dimension of the expandable and contractible closed cylinder body 20 can be arbitrarily set. Therefore, the output of the nuclear reactor can be controlled in the same manner as the conventional insertion and removal of control rods into the reactor core.

また、原子炉停止時にはポンプ22を停止させ、弁24
を全開すれば密閉筒体2oはその最大軸方向寸法となり
、従来の原子炉における制御棒全挿入と同様の状態とな
る。
Also, when the reactor is shut down, the pump 22 is stopped and the valve 24
When fully opened, the closed cylinder 2o has its maximum axial dimension, which is the same state as when the control rods are fully inserted in a conventional nuclear reactor.

さらに、燃料交換装置のアーム8はグリッパ11を偏心
位置にも移動させ得る構成としであるから、これを操作
して炉心のどの位置にある燃料の交換をも行うことがで
きる。
Furthermore, since the arm 8 of the fuel exchange device is configured to move the gripper 11 to an eccentric position, it can be operated to exchange fuel at any position in the core.

[発明の効果コ 上記から明らかなように本発明の液体リチウム制御式高
速増殖炉においては、燃料交換装置や制御棒駆動機構を
搭載して回転する回転プラグが不要となり1回転プラグ
に必須である多数の機器、設備が不要である。これによ
り、原子炉上部構造は著しく簡素化され、その設計、製
作、据付組立、試験検査等が簡単になり、高速増殖炉の
価格を低減させることができる。
[Effects of the Invention] As is clear from the above, the liquid lithium controlled fast breeder reactor of the present invention does not require a rotating plug equipped with a fuel exchange device or a control rod drive mechanism, which is essential for a single-rotation plug. A large number of devices and facilities are not required. This significantly simplifies the reactor superstructure, simplifies its design, manufacture, installation and assembly, testing and inspection, and reduces the cost of the fast breeder reactor.

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

第1図は本発明一実施例の原子炉停止間の燃料交換時に
おける縦断面図、第2図はその要部の拡大断面図、第3
図は従来の高速増殖炉の概略構成を示す断面図である。
FIG. 1 is a longitudinal sectional view of one embodiment of the present invention during fuel exchange during reactor shutdown, FIG. 2 is an enlarged sectional view of the main parts, and FIG.
The figure is a sectional view showing a schematic configuration of a conventional fast breeder reactor.

Claims (1)

【特許請求の範囲】[Claims] 液体金属冷却型高速増殖炉の炉心を収容する原子炉容器
の固定蓋中心を貫通して炉心の任意の部位に到達できる
燃料交換装置を設け、前記炉心外周領域には炉心軸に平
行なケースおよびこのケース内に収容され炉心軸方向に
伸縮可能な密閉筒体を有する制御体を配置し、前記密閉
筒体には液体リチウムのタンクを接続し、前記ケースに
はケース内の圧力を前記原子炉容器内の冷却材の給排に
より調整する制御装置を接続したことを特徴とする液体
リチウム制御式高速増殖炉。
A fuel exchange device is provided that can reach any part of the core by penetrating the center of the fixed lid of the reactor vessel housing the core of a liquid metal cooled fast breeder reactor, and a case and a case parallel to the core axis are provided in the outer peripheral region of the core. A control body having a sealed cylinder housed in the case and expandable and retractable in the axial direction of the reactor core is disposed, a liquid lithium tank is connected to the sealed cylinder, and the pressure inside the case is transferred to the reactor. A liquid lithium controlled fast breeder reactor, characterized in that it is connected to a control device that adjusts by supplying and discharging coolant in a container.
JP2247173A 1990-09-19 1990-09-19 Liquid lithium control type fast breeder Pending JPH04127087A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2247173A JPH04127087A (en) 1990-09-19 1990-09-19 Liquid lithium control type fast breeder

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2247173A JPH04127087A (en) 1990-09-19 1990-09-19 Liquid lithium control type fast breeder

Publications (1)

Publication Number Publication Date
JPH04127087A true JPH04127087A (en) 1992-04-28

Family

ID=17159529

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2247173A Pending JPH04127087A (en) 1990-09-19 1990-09-19 Liquid lithium control type fast breeder

Country Status (1)

Country Link
JP (1) JPH04127087A (en)

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