JPH0110637Y2 - - Google Patents

Info

Publication number
JPH0110637Y2
JPH0110637Y2 JP1982066910U JP6691082U JPH0110637Y2 JP H0110637 Y2 JPH0110637 Y2 JP H0110637Y2 JP 1982066910 U JP1982066910 U JP 1982066910U JP 6691082 U JP6691082 U JP 6691082U JP H0110637 Y2 JPH0110637 Y2 JP H0110637Y2
Authority
JP
Japan
Prior art keywords
fuel
chute
reactor vessel
transfer chamber
storage tank
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.)
Expired
Application number
JP1982066910U
Other languages
Japanese (ja)
Other versions
JPS58169594U (en
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 filed Critical
Priority to JP1982066910U priority Critical patent/JPS58169594U/en
Publication of JPS58169594U publication Critical patent/JPS58169594U/en
Application granted granted Critical
Publication of JPH0110637Y2 publication Critical patent/JPH0110637Y2/ja
Granted 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

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【考案の詳細な説明】 この考案は高速増殖炉における燃料交換用通路
構成に関する。
[Detailed Description of the Invention] This invention relates to a fuel exchange passage structure in a fast breeder reactor.

高速増殖炉の燃料交換装置の一つとして原子炉
容器と炉外燃料貯蔵槽に近接して燃料移送室を設
けると共に、原子炉容器並びに炉外燃料貯蔵槽に
延びる斜道を前記燃料移送室に開口させ、使用済
燃料、または新燃料を収納した燃料バケツトを燃
料移送室で中継し、斜道を介して原子炉容器内燃
料の出し入れをシユート式で行う装置が提案され
ている。
As one of the fuel exchange devices of the fast breeder reactor, a fuel transfer chamber is provided close to the reactor vessel and the ex-core fuel storage tank, and a slope extending to the reactor vessel and the ex-core fuel storage tank is connected to the fuel transfer chamber. A chute-type device has been proposed in which a fuel bucket containing spent fuel or new fuel is opened and relayed in a fuel transfer chamber, and fuel is transferred in and out of the reactor vessel via an inclined path.

この装置において設備される斜道の一般構成と
しては、原子炉容器、或いは炉外燃料貯蔵槽を貫
通して設けた斜孔内に燃料バケツトをガイドする
角管状のシユートを配装してなり、原子炉運転中
はこの斜道の燃料移送室に対する開口部を閉塞す
るようにしている。
The general configuration of the slope installed in this device is that a rectangular chute for guiding the fuel bucket is installed in a diagonal hole that penetrates the reactor vessel or the extra-core fuel storage tank. During reactor operation, the opening of this slope to the fuel transfer chamber is closed.

ところで、原子炉運転中、原子炉容器内に設け
た斜道の炉心に近い斜道下部の温度は約500℃に
も達し、原子炉の運転を停止して燃料の交換を行
う際にはこれが200℃またはこれ以下に低下する。
By the way, during reactor operation, the temperature at the bottom of the slope near the core of the slope installed inside the reactor vessel reaches approximately 500℃, and this temperature increases when the reactor is shut down and fuel is replaced. The temperature drops to 200℃ or below.

また、炉外燃料貯蔵槽についても、槽内の使用
済燃料の量によつてある程度の温度変化は避けら
れない。
Furthermore, in the out-of-core fuel storage tank, a certain degree of temperature change is unavoidable depending on the amount of spent fuel in the tank.

この温度変化のため、斜道を構成する角筒状の
シユートは熱による伸縮を生じ、これを吸収する
配慮が求められる。
Due to this temperature change, the rectangular cylindrical chute that makes up the slope expands and contracts due to heat, and consideration must be given to absorbing this.

従来はこのため、第5図に示すように、シユー
ト15下部においてシユートを分割し、軸方向に
伸縮可能に隙間19を形成した継手20が用いら
れている。
Conventionally, for this purpose, a joint 20 has been used in which the chute is divided at the lower part of the chute 15 and a gap 19 is formed so that the chute can be expanded and contracted in the axial direction, as shown in FIG.

しかし、これでは軸方向の変位しか吸収でき
ず、軸直角方向の変位による発生応力のため、斜
道強度を上げざるを得なかつたものである。
However, this method can only absorb displacement in the axial direction, and the stress generated by displacement in the direction perpendicular to the axis necessitates increasing the slope strength.

また、地震の発生で原子炉容器と斜道相互間に
相対的変位が生じるような場合にも、前記する従
来の継手構成では原子炉容器に対し過大な力が作
用する虞れもある。
Further, in the case where a relative displacement occurs between the reactor vessel and the slope due to an earthquake, there is a risk that excessive force will be applied to the reactor vessel with the above-mentioned conventional joint configuration.

この考案は上記の点に鑑みなされたものであつ
て、燃料交換装置の斜道を構成するシユートの軸
方向変位は勿論、軸直角方向の変位も巧に吸収で
きるようにし、原子炉容器の安全性を向上した斜
道構成を提供しようとするものである。
This idea was developed in view of the above points, and it is possible to skillfully absorb not only the axial displacement of the chute that constitutes the slope of the fuel exchange device, but also the displacement in the direction perpendicular to the axis, and to ensure the safety of the reactor vessel. The present invention aims to provide a slope configuration with improved performance.

以下、この考案の実施例を図面について説明す
る。
Hereinafter, embodiments of this invention will be described with reference to the drawings.

第1図はこの考案を適用した原子炉全体構成を
概略的に示すもので、1は原子炉容器、2は炉
心、3は原子炉容器1に隣接して設けた炉外燃料
貯蔵槽、4は原子炉容器1及び燃料貯蔵槽3を結
んで設けた気密及び遮蔽機能を備えた燃料移送室
を示す。
Figure 1 schematically shows the overall configuration of a nuclear reactor to which this invention is applied, in which 1 is a reactor vessel, 2 is a reactor core, 3 is an extra-core fuel storage tank provided adjacent to the reactor vessel 1, and 4 is a nuclear reactor. 1 shows a fuel transfer chamber that connects the reactor vessel 1 and the fuel storage tank 3 and has an airtight and shielding function.

5,6は燃料移送室4に各上端を開口させて前
記炉心2と炉外燃料貯蔵槽3間に対向的に設けた
斜道、7はこの二つの斜道5,6の何れかの開口
位置に達して連結状となる可動トラツク、8は燃
料バケツトで、支持架台9上に設けた巻取りドラ
ム10から延びる索条11に連結されて可動トラ
ツク7に出入りし、また、斜道5,6内を昇降し
て燃料を運ぶようにしたものである。
Reference numerals 5 and 6 denote slopes which are opened at the upper ends of the fuel transfer chamber 4 and are provided oppositely between the core 2 and the external fuel storage tank 3, and 7 is an opening of either of the two slopes 5 and 6. The movable truck 8 is a fuel bucket, which is connected to a cable 11 extending from a winding drum 10 mounted on a support frame 9 to move in and out of the movable track 7. The fuel is transported by going up and down inside the tank.

尚、図中12は原子炉容器1上に設置した炉内
燃料交換装置、13は炉外燃料貯蔵槽3上に設置
した炉外燃料交換装置を示す。
In the figure, reference numeral 12 indicates an in-core fuel exchange device installed on the reactor vessel 1, and 13 indicates an ex-core fuel exchange device installed on the extra-core fuel storage tank 3.

さて、この考案において、斜道5,6は、原子
炉容器1、並びに炉外燃料貯蔵槽3を貫通して設
けた斜孔14と、該斜孔14内に配装した角筒状
シユート15を以て構成するが、このシユート1
5の下部でシユート15を分割構成にすると共
に、複数個の短管体16を直列状に配列し、これ
等短管体16同士、及びシユート下端部と短管体
16をその対向2面縁部で屈曲自在にピン7結合
してなる可撓性部18を挿設し、該可撓性部18
に続いて若干の隙間19を形成した継手20を形
成したものである。
Now, in this invention, the slopes 5 and 6 are formed by a diagonal hole 14 provided through the reactor vessel 1 and the external fuel storage tank 3, and a rectangular cylindrical chute 15 disposed within the diagonal hole 14. This shoot 1
The chute 15 is divided into parts at the lower part of the chute 5, and a plurality of short tube bodies 16 are arranged in series, and these short tube bodies 16 and the lower end of the chute and the short tube body 16 are connected to opposite two-sided edges. A flexible part 18 formed by connecting the pin 7 in a freely bendable manner is inserted, and the flexible part 18
Subsequently, a joint 20 with a slight gap 19 is formed.

尚、可撓性部18における各短管体16相互間
には屈曲を自由とする上から隙間21が形成され
るが、これは燃料バケツト8の通過に当たつてそ
の車輪が容易に乗り越えられる範囲に設定する。
Incidentally, a gap 21 is formed from above between each of the short tube bodies 16 in the flexible part 18 to allow free bending, but this allows the wheels of the fuel bucket 8 to easily overcome this gap. Set to range.

上記構成において、この考案によれば、原子炉
運転及び運転停止に基づく温度変化によつて生じ
る斜道構成要素とするシユート15の熱変位はそ
の軸方向は勿論、軸直角方向に対しても可撓性部
18によつて吸収するものである。
In the above configuration, according to this invention, thermal displacement of the chute 15, which is a slope component, caused by temperature changes due to reactor operation and shutdown can be caused not only in the axial direction but also in the direction perpendicular to the axis. This is absorbed by the flexible portion 18.

従つて、シユート関連各部には無駄な力が掛か
らず、斜道強度設計上からして有利となり、地震
発生時に原子炉に過大な力が掛かることがあつて
も、これが斜道を介して外部へ波及することも極
力防止できて、対地震対策からしても有効なもの
である。
Therefore, unnecessary force is not applied to the chute-related parts, which is advantageous from the viewpoint of slope strength design, and even if excessive force is applied to the reactor in the event of an earthquake, this will not be applied to the outside via the slope. It is also effective in terms of earthquake countermeasures, as it can prevent the damage from spreading to others as much as possible.

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

第1図はこの考案の斜道を適用した燃料交換装
置の全体構成図、第2図は要部の側面図、第3図
は平面図、第4図は第3図a−a線における断面
図、第5図は従来例の一部側面図である。 1……原子炉容器、2……炉心、3……炉外燃
料貯蔵槽、4……燃料移送室、5,6……斜道、
7……可動トラツク、8……燃料バケツト、9…
…支持架台、10……巻取ドラム、11……索
条、12,13……燃料交換装置、14……斜
孔、15……シユート、16……短管体、17…
…ピン、18……可撓性部、19……隙間、20
……継手、21……隙間。
Fig. 1 is an overall configuration diagram of a fuel exchange device to which the slope of this invention is applied, Fig. 2 is a side view of the main parts, Fig. 3 is a plan view, and Fig. 4 is a cross section taken along line a-a in Fig. 3. FIG. 5 is a partial side view of a conventional example. 1...Reactor vessel, 2...Reactor core, 3...External fuel storage tank, 4...Fuel transfer chamber, 5, 6...Slope,
7...Movable truck, 8...Fuel bucket, 9...
... Support frame, 10 ... Winding drum, 11 ... Cable, 12, 13 ... Fuel exchange device, 14 ... Diagonal hole, 15 ... Chute, 16 ... Short tube body, 17 ...
... Pin, 18 ... Flexible part, 19 ... Gap, 20
...Joint, 21...Gap.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 原子炉容器と炉外燃料貯蔵槽に近接して燃料移
送室を設け、該燃料移送室で燃料バケツトを中継
し、斜道を介して原子炉容器内の燃料の出し入れ
をシユート方式で行う燃料交換装置において、原
子炉容器内と燃料移送室を結ぶ斜道、並びに炉外
燃料貯蔵槽と燃料移送室を結ぶ斜道を、炉容器ま
たは貯蔵槽を貫通して設けた斜孔と、該斜孔内に
配装した燃料バケツトをガイドする角管状シユー
トを以て構成し、該シユート下端部に複数個の短
管体を直列状に配列し、短管体同士及びシユート
下端部と短管体をその対向2面縁部で屈曲自在に
ピン結合してなる可撓性部を挿設したことを特徴
とする高速増殖炉における燃料交換用通路構成。
A fuel exchange system in which a fuel transfer chamber is provided close to the reactor vessel and the external fuel storage tank, a fuel bucket is relayed in the fuel transfer chamber, and fuel is transferred in and out of the reactor vessel via a slope using a chute method. In the device, a diagonal hole is provided through the reactor vessel or the storage tank to provide a diagonal path connecting the inside of the reactor vessel and the fuel transfer chamber, and a diagonal path connecting the external fuel storage tank and the fuel transfer chamber, and the diagonal hole. It consists of a rectangular tubular chute that guides the fuel bucket placed inside the chute, and a plurality of short tube bodies are arranged in series at the lower end of the chute, and the short tube bodies and the lower end of the chute and the short tube bodies are arranged opposite to each other. A fuel exchange passage structure in a fast breeder reactor, characterized in that a flexible part is inserted which is formed by bendably pin-coupled at the edges of two sides.
JP1982066910U 1982-05-08 1982-05-08 Fuel exchange passage configuration in fast breeder reactor Granted JPS58169594U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1982066910U JPS58169594U (en) 1982-05-08 1982-05-08 Fuel exchange passage configuration in fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1982066910U JPS58169594U (en) 1982-05-08 1982-05-08 Fuel exchange passage configuration in fast breeder reactor

Publications (2)

Publication Number Publication Date
JPS58169594U JPS58169594U (en) 1983-11-12
JPH0110637Y2 true JPH0110637Y2 (en) 1989-03-27

Family

ID=30076754

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1982066910U Granted JPS58169594U (en) 1982-05-08 1982-05-08 Fuel exchange passage configuration in fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS58169594U (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2504446B2 (en) * 1987-03-06 1996-06-05 株式会社日立製作所 Fuel access device

Also Published As

Publication number Publication date
JPS58169594U (en) 1983-11-12

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