JPS62172292A - Controller for gas cooling type reactor - Google Patents
Controller for gas cooling type reactorInfo
- Publication number
- JPS62172292A JPS62172292A JP61013685A JP1368586A JPS62172292A JP S62172292 A JPS62172292 A JP S62172292A JP 61013685 A JP61013685 A JP 61013685A JP 1368586 A JP1368586 A JP 1368586A JP S62172292 A JPS62172292 A JP S62172292A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- control
- guide tube
- reactor vessel
- drive device
- 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
- 238000001816 cooling Methods 0.000 title 1
- 238000005253 cladding Methods 0.000 description 9
- 239000000446 fuel Substances 0.000 description 6
- 239000011358 absorbing material Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 230000035939 shock 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
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】
（産業上の利用分野）
本発明はガス冷却型原子炉の制御装置に関するものであ
る。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a control device for a gas-cooled nuclear reactor.
（従来の技術）
従来のガス冷却型原子炉の制御装置を第４，５図により
説明すると、 （０１）が二次生体ｙＸ、蔽部、（０２
）が−次生体遮蔽部、 （０３）がスタンドバイブクロ
ージャ、 （０４）がスタンドバイブ、 （０５）が制
御棒駆動装置、 （０６）が制御棒案内管、 （０７）
が制御棒。(Prior art) A conventional control system for a gas-cooled nuclear reactor will be explained with reference to FIGS. 4 and 5. (01) is the secondary body yX, the shield part,
) is the second biological shielding part, (03) is the stand vibe closure, (04) is the stand vibe, (05) is the control rod drive device, (06) is the control rod guide tube, (07)
is the control rod.
（０７ａ）が同制御棒（０７）の被覆管、 （０７ｂ）
が同被覆管（０７ａ）内の中性子吸収材、 （０７ｃ）
が軸棒、 （０８）が炉心、 （０９）が原子炉容器、
（０９ａ）が同原子炉容器（０９）の上部蓋、 （０
１０）が上記制御棒駆動装置（０５）から下方に延びた
ワイヤローブ、（０１１）がショックアブソーバで、制
御棒駆動装置（０５）がスタンドバイブ（０４）内に設
置され、ワイヤローブ（０１０）が同制御棒駆動装置（
０５）から制御棒案内管（０６）内を経て原子炉容器（
０９）内へ延び、制御棒（０７）が同ワイヤロープ（０
１０）に接続されて、同制御棒（０７）が燃料交換を行
うときの最高位置と制御を行うときの最低位置（（０７
’）参照）との間に昇降可能になっている。(07a) is the cladding tube of the control rod (07), (07b)
is the neutron absorbing material inside the cladding tube (07a), (07c)
is the shaft rod, (08) is the reactor core, (09) is the reactor vessel,
(09a) is the upper lid of the reactor vessel (09), (0
10) is a wire lobe extending downward from the control rod drive device (05), (011) is a shock absorber, the control rod drive device (05) is installed in the stand vibe (04), and the wire lobe (010) is the same. Control rod drive device (
05) through the control rod guide tube (06) to the reactor vessel (
09), and the control rod (07) extends into the same wire rope (0
10), and the control rod (07) is connected to the highest position when performing fuel exchange and the lowest position when performing control ((07)
') Reference) It is possible to go up and down between.
（発明が解決しようとする問題点）
前記制御棒（０７）は、°制御を行う最低位置く（０７
′）参照）に下降したとき、炉心（０８）の高さに相当
した長さを必要としているが、燃料交換を行う最高位置
に上昇したときには、その長さを保持する必要がない。(Problems to be Solved by the Invention) The control rod (07) is located at the lowest position (07) for performing ° control.
When it descends to the height of the core (08), it needs to have a length corresponding to the height of the core (08), but when it ascends to the highest position where fuel exchange is performed, it does not need to maintain that length.
ところが前記第４．５図に示す従来のガス冷却型原子炉
の制御装置では、燃料交換を行う最高位置でも、制御を
行う最低位置（（０７”）参照）でも、制御棒（０７）
の長さが変わらないので。However, in the conventional gas-cooled nuclear reactor control system shown in Fig. 4.5, the control rods (07)
Because the length of is unchanged.
■制御棒案内管（０６）及びスタンドパイプ（０４）の
長さを長くする必要がある。■−次生体遮蔽部（０２）
と原子炉容器上部Ｍ（０９ａ）との間の間隔を大きくす
る必要があって、原子炉容器（０９）と、制御棒（０７
）を含む制御棒駆動装置（０５）ユニットと、燃料交換
機（図示せず）とが大型化するという問題があった。■It is necessary to increase the length of the control rod guide tube (06) and stand pipe (04). ■-Next living body shielding part (02)
It is necessary to increase the distance between the reactor vessel (09) and the upper part M (09a) of the reactor vessel (09a).
) There was a problem in that the control rod drive unit (05) including the fuel exchanger (not shown) and the fuel exchanger (not shown) became large in size.
（問題点を解決するための手段）
本発明は前記の問題点に対処するもので、多数の筒状部
材を軸方向に伸縮可能に組付けて構成した制御棒を有し
、同制御棒を原子炉容器の上部蓋よりも上方に位置する
制御棒駆動装置から下方に延びたワイヤローブと同原子
炉容器上部盈から下方に延びた制御棒案内管とにより昇
降可能に支持し、同制御棒案内管内の上部に制御棒スト
ッパを設けたことを特徴とするガス冷却型原子炉の制御
装置に係わり、その目的とする処は、制御棒案内管及び
スタンドバイブを短尺化できる。また原子炉容器、制御
棒を含む制御棒駆動装置ユニット。(Means for Solving the Problems) The present invention addresses the above-mentioned problems, and includes a control rod constructed by assembling a large number of cylindrical members so as to be expandable and retractable in the axial direction. The control rod guide is supported in a vertically movable manner by a wire lobe extending downward from the control rod drive device located above the upper cover of the reactor vessel and a control rod guide tube extending downward from the upper shell of the reactor vessel. This invention relates to a control device for a gas-cooled nuclear reactor characterized by a control rod stopper provided at the upper part of the tube, and its purpose is to shorten the length of the control rod guide tube and stand vibrator. Also a control rod drive unit including the reactor vessel and control rods.
燃料交換機等を小型化できる改良されたガス冷却型原子
炉の制御装置を供する点にある。An object of the present invention is to provide an improved control device for a gas-cooled nuclear reactor that can downsize a fuel exchanger and the like.
（作用）
本発明のガス冷却型原子炉の制御装置は前記のように構
成されており、制御棒駆動装置を駆動して、ワイヤロー
ブを繰り出すと、制御棒が下降し。(Function) The control device for a gas-cooled nuclear reactor of the present invention is configured as described above, and when the control rod drive device is driven to extend the wire lobe, the control rod descends.
制御棒の上端部が制御棒案内管の下端部に設けた制御棒
ストッパに係合して、制御棒が最低位置に保持される。The upper end of the control rod engages with a control rod stopper provided at the lower end of the control rod guide tube to hold the control rod at the lowest position.
このとき、制御棒の各筒状部材（制御棒要素）は、軸方
向（上下方向）に延びて、その長さが炉心の高さに略等
しくなる。また制御棒駆動装置を駆動して、ワイヤロー
ブを引き上げると、制御棒の各筒状部材（制御棒要素）
が軸方向に縮み、ワイヤローブをさらに引き上げると、
制御棒が制御棒案内管内を上昇し、最終的には、最上段
の筒状部材がスタンドパイプ内下部に入って停止する。At this time, each cylindrical member (control rod element) of the control rod extends in the axial direction (vertical direction), and its length becomes approximately equal to the height of the reactor core. Also, when the control rod drive device is driven and the wire lobe is pulled up, each cylindrical member of the control rod (control rod element)
contracts in the axial direction and as the wire lobe is pulled up further,
The control rod moves up inside the control rod guide tube, and eventually the uppermost cylindrical member enters the lower part of the standpipe and stops.
（実施例）
次に本発明のガス冷却型原子炉の制御装置を第１．２．
３図に示す一実施例により説明すると２（１）が二次生
体遮蔽部、（２）が−次生体遮蔽部、（３）がスタンド
パイプクロージャ、（４）がスタンドバイブ、（５）が
制御棒駆動装置、（６）が制御棒案内管、（６ａ）が同
制御棒案内管（６）の下端部に設けたフランジ（制御棒
ストッパ）、（７）が制御棒で、同制御棒（７）が多数
の被覆を（７ａ）と同各被覆管（７ａ）内の中性子吸収
材（７ｂ）と各被覆管（７ａ）を軸方向に伸縮可能に連
結する連結部（７ｅ）と最上部の被覆管（７ａ）に昇降
可能（伸縮可能）に取付けた制御棒ストッパ（７ｄ）と
により構成されて、同制御棒（７）が軸方向に伸縮可能
になっている。なお上記制御棒ストッパ（７ｄ）の上端
部には、鍔部（７ｄｌ）があり、これが制御棒案内管（
６）の下端部に設けたフランジにｉ；＋１１１１１棒ス
トツパ） （６ａ）に係合して、 ；％１１ ？１１１
棒（７）が最低位置に保持される。また（８）が炉心、
（９）が原子炉容器、 （９ａ）が同原子炉容器（９）
の上部蓋１（１０）が上記制御棒駆動装置（０５）から
下方に延びたワイヤローブで、制御棒駆動装置（５）が
スタンドバイブ（４）内に設置され１ワイヤローブ（１
０）が同制御棒駆動装置（０５）から制御棒案内管（６
）内を経て原子炉容器（９）内へ延び、さらに制御棒（
７）内を貫通して、ワイヤローブ（１０）の下端部が制
御棒（７）の下端部に取付けられている。(Example) Next, the control device for a gas-cooled nuclear reactor of the present invention will be described in Section 1.2.
To explain with an example shown in Fig. 3, 2(1) is a secondary living body shielding part, (2) is a second living body shielding part, (3) is a stand pipe closure, (4) is a stand vibe, and (5) is a Control rod drive device, (6) is a control rod guide tube, (6a) is a flange (control rod stopper) provided at the lower end of the control rod guide tube (6), (7) is a control rod, and (6) is a control rod guide tube. (7) connects a large number of coatings to (7a) and the connecting portion (7e) that connects the neutron absorbing material (7b) in each cladding tube (7a) and each cladding tube (7a) so as to be expandable and contractible in the axial direction. The control rod (7) is configured with a control rod stopper (7d) attached to the upper cladding tube (7a) so as to be movable (expandable) up and down, so that the control rod (7) can be expanded and contracted in the axial direction. There is a flange (7dl) at the upper end of the control rod stopper (7d), which is connected to the control rod guide tube (7dl).
6) Engage with the flange provided at the lower end of i;+11111 bar stopper) (6a), ;%11? 111
The rod (7) is held in the lowest position. Also, (8) is the core,
(9) is the reactor vessel, (9a) is the reactor vessel (9)
The upper lid 1 (10) is a wire lobe extending downward from the control rod drive device (05), and the control rod drive device (5) is installed in the stand vibe (4) and has one wire lobe (1
0) is connected from the control rod drive device (05) to the control rod guide tube (6
) into the reactor vessel (9), and then the control rods (
7) The lower end of the wire lobe (10) is attached to the lower end of the control rod (7) through the inside.
次に前記第１．２．３図に示すガス冷却型原子炉の制御
装置の作用を具体的に説明する。制御棒駆動装置（５）
を駆動して、ワイヤローブ（１０）を操り出すと、制御
棒（７）が下降し、制御棒ストッパ（７ｄ）の上端部に
設けた鍔部（７ｄ＋）が制御棒案内管（６）の下端部に
設けたフランジ（制御棒ストッパ） （６ａ）に係合し
て、制御棒（７）が最低位置に保持される。このとき、
制御棒（７）の各被覆管（７ａ）（制御棒要素）は、第
２図のように軸方向（上下方向）に延びて、その長さが
炉心（８）の亮さに略等しくなる。また制御棒駆動装置
（５）を駆動して。Next, the operation of the control system for the gas-cooled nuclear reactor shown in FIG. 1.2.3 will be explained in detail. Control rod drive device (5)
When the wire lobe (10) is pulled out, the control rod (7) descends, and the flange (7d+) provided at the upper end of the control rod stopper (7d) connects to the lower end of the control rod guide tube (6). The control rod (7) is held at the lowest position by engaging with the flange (control rod stopper) (6a) provided at the section. At this time,
Each cladding tube (7a) (control rod element) of the control rod (7) extends in the axial direction (vertical direction) as shown in Figure 2, and its length is approximately equal to the brightness of the reactor core (8). . Also, drive the control rod drive device (5).
ワイヤローブ（１０）を引き上げると、制御棒（７）の
各被覆管（７ａ） （制御棒要素）が軸方向に縮み、ワ
イヤローブ（１０）をさらに上昇させると、制御棒スト
ッパ（７ｄ）の鍔部（７ｄ＋）が制御棒案内管（６）の
下端部に設けたフランジ（６ａ）から離れて上昇し、同
制御棒ストッパ（７ｄ）が最上段の被覆管（７ａ）内に
下降して１制御棒（７）の全体が最小長さに縮み、それ
からはこの縮小状態を保って１制御棒案内管（６）内を
上昇し、最終的には、第３図のように最上段の被覆管（
７ａ）及び制御棒ストッパ（７ｄ）がスタンドバイブ（
４）内下部に入って停止する。When the wire lobe (10) is raised, each cladding tube (7a) (control rod element) of the control rod (7) contracts in the axial direction, and when the wire lobe (10) is further raised, the flange of the control rod stopper (7d) (7d+) separates from the flange (6a) provided at the lower end of the control rod guide tube (6) and rises, and the control rod stopper (7d) descends into the uppermost cladding tube (7a) for one control. The entire rod (7) is shrunk to its minimum length, and then maintains this shrunken state as it ascends through the first control rod guide tube (6), and finally reaches the top cladding tube as shown in Figure 3. (
7a) and the control rod stopper (7d) are connected to the stand vibe (
4) Enter the inner lower part and stop.
（発明の効果）
本発明のガス冷却型原子炉の制御装置は前記のように制
御棒駆動装置を駆動して、ワイヤローブを繰り出し、制
′４′ｌｌｌ棒を下降させ、制御棒の上端部を制御棒案
内管の下端部に設けた制御棒ストッパに係合して、制御
棒を最低位置に保持する。このとき、制御棒の各筒状部
材（制御棒要素）は、軸方向（上下方向）に延びて、そ
の長さが炉心の高さに略等しくなる。また制御棒駆動装
置を駆動して１ ワイヤローブを引き上げ、制御棒の各
筒状部材（制御棒要素）を軸方向に縮小させて、最終的
には、最上段の筒状部材をスタンドバイブ内下部に入れ
るので、−次生体遮蔽部部と原子炉容器上部蓋との間の
間隔を小さくできて、制御棒案内管及びスタンドバイブ
を短尺化できる。また上記のように一次生体遮蔽部部と
原子炉容器上部蓋との間の間隔を小さくできるので、原
子炉容器、制御棒を含む制御棒駆動装置ユニット燃料交
換機等を小型化できる効果がある。(Effects of the Invention) The control device for a gas-cooled nuclear reactor of the present invention drives the control rod drive device as described above, extends the wire lobe, lowers the control rod, and moves the upper end of the control rod. The control rod is engaged with a control rod stopper provided at the lower end of the control rod guide tube to hold the control rod in the lowest position. At this time, each cylindrical member (control rod element) of the control rod extends in the axial direction (vertical direction), and its length becomes approximately equal to the height of the reactor core. In addition, the control rod drive device is driven to pull up the wire lobe, reduce each cylindrical member of the control rod (control rod element) in the axial direction, and finally move the uppermost cylindrical member to the lower part of the stand vibe. Since the control rod guide tube and the stand vibrator can be placed in a small space, the distance between the secondary biological shielding section and the upper lid of the reactor vessel can be reduced, and the length of the control rod guide tube and stand vibrator can be shortened. Further, as described above, since the distance between the primary biological shielding section and the reactor vessel upper cover can be reduced, there is an effect that the reactor vessel, the control rod drive unit including the control rods, the fuel exchanger, etc. can be downsized.
以上本発明を実施例により説明したが、勿論本発明はこ
のような実施例にだけ局限されるものでなく２本発明の
精神を逸脱しない範囲内で種々の設計の改変を施しうる
ちのである。The present invention has been described above with reference to examples, but of course the present invention is not limited to these examples and can be modified in various ways without departing from the spirit of the invention. .
第１図は本発明に係わるガス冷却型原子炉の制御装置の
一実施例を示す縦断側面図、第２図は第１図矢印■部分
の拡大縦断側面図、第３図は第１図の矢印ｍ部分の拡大
縦断側面図、第４図は従来のガス冷却型原子炉の制御装
置を示す縦断側面図。
第５図は第４図の矢印７部分の拡大縦断側面図である。
（５）・・・制御棒駆動装置、（６）・・・制御棒案内
管、 （６ａ） ・・・制御棒ストッパ、（７）・・
・制御棒。
（７ａ）・・・筒状部材１（９）・・・原子炉容器、（
９ａ）・・・原子炉容器（９）の上部蓋、 （１０）
・・・ワイヤローブ。
復代理人弁理士岡本重文外２名FIG. 1 is a vertical side view showing an embodiment of the control device for a gas-cooled nuclear reactor according to the present invention, FIG. 2 is an enlarged vertical side view of the arrow ■ in FIG. 1, and FIG. FIG. 4 is an enlarged vertical side view of the arrow m portion, and FIG. 4 is a vertical side view showing a conventional control device for a gas-cooled nuclear reactor. FIG. 5 is an enlarged longitudinal sectional side view of the portion indicated by arrow 7 in FIG. (5)... Control rod drive device, (6)... Control rod guide tube, (6a)... Control rod stopper, (7)...
・Control rod. (7a)...Cylindrical member 1 (9)...Reactor vessel, (
9a)...Top lid of reactor vessel (9), (10)
...wire robe. Sub-representative patent attorney Shigefumi Okamoto and two others
Claims (1)
制御棒を有し、同制御棒を原子炉容器の上部蓋よりも上
方に位置する制御棒駆動装置から下方に延びたワイヤロ
ープと同原子炉容器上部蓋から下方に延びた制御棒案内
管とにより昇降可能に支持し、同制御棒案内管内の上部
に制御棒ストッパを設けたことを特徴とするガス冷却型
原子炉の制御装置。The control rod is constructed by assembling a number of cylindrical members that can be expanded and contracted in the axial direction, and the control rod is connected to a wire rope that extends downward from a control rod drive device located above the upper lid of the reactor vessel. and a control rod guide tube extending downward from the upper lid of the reactor vessel, the control rods are supported so as to be movable up and down, and a control rod stopper is provided at the upper part of the control rod guide tube. Device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61013685A JPS62172292A (en) | 1986-01-27 | 1986-01-27 | Controller for gas cooling type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61013685A JPS62172292A (en) | 1986-01-27 | 1986-01-27 | Controller for gas cooling type reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62172292A true JPS62172292A (en) | 1987-07-29 |
Family
ID=11840040
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61013685A Pending JPS62172292A (en) | 1986-01-27 | 1986-01-27 | Controller for gas cooling type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62172292A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016529521A (en) * | 2013-09-03 | 2016-09-23 | チングア ユニバーシティー | Reactive control method and telescope type control rod of pebble bed high temperature gas cooling furnace |
-
1986
- 1986-01-27 JP JP61013685A patent/JPS62172292A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016529521A (en) * | 2013-09-03 | 2016-09-23 | チングア ユニバーシティー | Reactive control method and telescope type control rod of pebble bed high temperature gas cooling furnace |
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