JPH0476076B2 - - Google Patents

Info

Publication number
JPH0476076B2
JPH0476076B2 JP59124688A JP12468884A JPH0476076B2 JP H0476076 B2 JPH0476076 B2 JP H0476076B2 JP 59124688 A JP59124688 A JP 59124688A JP 12468884 A JP12468884 A JP 12468884A JP H0476076 B2 JPH0476076 B2 JP H0476076B2
Authority
JP
Japan
Prior art keywords
control rod
guide tube
crd
core
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.)
Expired - Lifetime
Application number
JP59124688A
Other languages
Japanese (ja)
Other versions
JPS613084A (en
Inventor
Yoshio Imazaki
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
Tokyo Shibaura 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP59124688A priority Critical patent/JPS613084A/en
Publication of JPS613084A publication Critical patent/JPS613084A/en
Publication of JPH0476076B2 publication Critical patent/JPH0476076B2/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)
  • Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)

Description

【発明の詳細な説明】 [発明の技術分野] 本発明は、制御棒と制御棒駆動機構との着脱
を、相互に所定角度回転させることにより可能と
する沸騰水型原子炉(以下BWRと称する)の改
良に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a boiling water reactor (hereinafter referred to as BWR) in which a control rod and a control rod drive mechanism can be attached and detached by mutually rotating a predetermined angle. ) related to improvements.

[発明の技術的背景] BWRは、第5図に示すように冷却材(軟水)
を収容する原子炉圧力容器1の内部に炉心シユラ
ウド2が設けられ、この炉心シユラウド2内に設
けられた炉心支持板3上に多数の燃料集合体4を
装荷して炉心5が構成されている。上記各燃料集
合体4は角筒状のチヤンネルボツクス内に多数の
燃料棒を収容してなるもので、平面図上において
は炉心シユラウド2内にマトリツクス状になるよ
うに配列されており、原子炉圧力容器1内の底部
より上方へ向つて流通する冷却材を核反応熱で加
熱する。また炉心5には制御棒(以下CRと称す
る)6が配設されている。このCR6は、第6図
および第7図に示す如く中性子吸収物質を内蔵し
た4枚のフインガ6aを断面が十字形となるよう
に組合せてなるもので、上記4枚のフインガ6a
をそれぞれ隣接する燃料集合体4間に介在させ
て、4体の燃料集合体4に対し1体の割合で配置
されている。そして各CR6を上記燃料集合体4
間に下方より挿入することによりその挿入量に応
じて炉心出力が制御され、また各CR6を上記燃
料集合体4間より下方へ引抜くことにより炉心出
力が高められて、原子炉運転時における出力制御
が行なわれる構成となつている。
[Technical background of the invention] BWR uses coolant (soft water) as shown in Figure 5.
A core shroud 2 is provided inside a reactor pressure vessel 1 that accommodates a reactor, and a reactor core 5 is constructed by loading a large number of fuel assemblies 4 onto a core support plate 3 provided within this core shroud 2. . Each of the fuel assemblies 4 is made up of a large number of fuel rods housed in a rectangular cylindrical channel box, and in a plan view, they are arranged in a matrix within the core shroud 2, and are arranged in a matrix in the reactor core shroud 2. The coolant flowing upward from the bottom of the pressure vessel 1 is heated by nuclear reaction heat. Further, control rods (hereinafter referred to as CR) 6 are arranged in the reactor core 5 . As shown in FIGS. 6 and 7, this CR6 is constructed by combining four fingers 6a containing a neutron absorbing material so that the cross section is cross-shaped.
are arranged between adjacent fuel assemblies 4, with one fuel assembly for every four fuel assemblies 4. Then each CR6 is attached to the fuel assembly 4 above.
By inserting each CR6 from below between the fuel assemblies 4, the core output is controlled according to the insertion amount, and by pulling each CR6 downward from between the fuel assemblies 4, the core output is increased, and the output during reactor operation is increased. The configuration is such that control is performed.

また第5図中7は上記炉心5の下方に各CR6
ごとに対応して設けられた円筒形状の制御棒案内
管(以下CR案内管と称する)で、このCR案内管
7は第7図に示す如く各CR6を内部に挿通させ、
原子炉通常運転時に昇降動作するCR6の案内を
するものである。そして原子炉圧力容器1の下方
にはCR6を昇降駆動する制御棒駆動機構(以下
CRDと称する)8が設けられている。
In addition, 7 in Fig. 5 indicates each CR6 below the core 5.
A cylindrical control rod guide tube (hereinafter referred to as CR guide tube) is provided corresponding to each CR guide tube 7, and each CR6 is inserted into the CR guide tube 7 as shown in FIG.
It guides the CR6, which moves up and down during normal reactor operation. Below the reactor pressure vessel 1 is a control rod drive mechanism (hereinafter referred to as
(referred to as CRD) 8 is provided.

前記炉心シユラウド2の上端はシユラウドヘツ
ド9で閉塞されており、そのシユラウドヘツド9
上には気水分離器10が接続されている。この気
水分離器10は炉心5で加熱されて蒸発した冷却
材蒸気を気水分離するものであり、さらに気水分
離器10上には、気水分離された蒸気を乾燥させ
る蒸気乾燥器11が接続されている。そして蒸気
乾燥器11を通過した蒸気は、図示しない主蒸気
管を通して原子炉容器1外の発電機駆動用タービ
ンへ送出される。
The upper end of the core shroud 2 is closed with a shroud head 9.
A steam separator 10 is connected to the top. This steam-water separator 10 separates the coolant vapor heated and evaporated in the core 5 into steam and water, and further above the steam-water separator 10 is a steam dryer 11 for drying the separated steam. is connected. The steam that has passed through the steam dryer 11 is sent to a generator-driving turbine outside the reactor vessel 1 through a main steam pipe (not shown).

前記CR案内管7は、第8図に示すように炉心
支持板3を貫通してその上端外周部を炉心支持板
3に支持され、さらにその上端部を炉心支持板3
の上面側に突設されたピン12に係合させてその
回転が禁止されている。また各CR案内管7の上
端四隅部には、それぞれ燃料集合体4を下方より
支持する燃料サポート13が形成されている。さ
らにCR案内管7の内周面下端部にはCR6の下端
部を着座させるシート面14が設けられている。
As shown in FIG. 8, the CR guide tube 7 passes through the core support plate 3, has its upper end outer periphery supported by the core support plate 3, and further has its upper end supported by the core support plate 3.
Its rotation is prohibited by engagement with a pin 12 protruding from the upper surface of the holder. Furthermore, fuel supports 13 are formed at the four corners of the upper end of each CR guide tube 7 to support the fuel assembly 4 from below. Furthermore, a seat surface 14 is provided at the lower end of the inner peripheral surface of the CR guide tube 7 on which the lower end of the CR 6 is seated.

前記CRD8は第8図に示す如く円筒形状の制
御棒駆動ハウジング(以下CRDハウジングと称
する)15に収容支持されている。CRDハウジ
ング15は、原子炉圧力容器1の底部鏡板1aを
貫通してこの底部鏡板1aに溶接されているもの
で、CRD8は上記CRDハウジング15内に収容
されるピストン16と、このピストン16を昇降
駆動するモータ部17とを有し、モータ部17を
CRDハウジング15の下方に露出させた状態で、
CRDハウジング15の下端フランジ部15aに
ボルト等により取付けられている。
The CRD 8 is housed and supported in a cylindrical control rod drive housing (hereinafter referred to as CRD housing) 15, as shown in FIG. The CRD housing 15 penetrates the bottom head plate 1a of the reactor pressure vessel 1 and is welded to the bottom head plate 1a. It has a motor section 17 that drives the motor section 17.
With the CRD housing 15 exposed below,
It is attached to the lower end flange portion 15a of the CRD housing 15 with bolts or the like.

前記CRD8の上端はCR6の下端に着脱自在に
連結されるが、このような連結機構には種々のも
のがある。第9図a,bおよび第10図a,bに
その一例を示す。すなわち、CRD8のピストン
16上端には周方向等間隔に配置された4本のた
て長な係合片18aよりなるバヨネツト式連結部
18が設けられ、各係合片18aの外面先端部に
は膨出部18bが形成されている。さらに、上記
4本の係合片18aの中央には支持棒18cが上
方向へ向つて突設され、この支持棒18cで4本
の係合片18aの内方へのたわみ量を制限するよ
うにしている。一方、CR6の下端には上記連結
部18を収容する凹所19aが設けられ、その凹
所19aの内周面開口端部には上記各係合片18
aに対応するように4つの係合突起19bを周方
向間隔に突出させてバヨネツト式被連結部19が
構成されている。そして上記連結部18と被連結
部19とが連結された状態では凹所19aの底面
が支持棒18cに当接し、CR6の重量が支持棒
18cによつて支持されるようになる。
The upper end of the CRD 8 is detachably connected to the lower end of the CR 6, and there are various types of such connection mechanisms. Examples are shown in FIGS. 9a and 9b and 10a and 10b. That is, the upper end of the piston 16 of the CRD 8 is provided with a bayonet type connecting portion 18 consisting of four vertically long engaging pieces 18a arranged at equal intervals in the circumferential direction, and the outer end of each engaging piece 18a has a bayonet type connecting portion 18. A bulging portion 18b is formed. Furthermore, a support rod 18c is provided at the center of the four engagement pieces 18a to project upward, and this support rod 18c limits the amount of inward deflection of the four engagement pieces 18a. I have to. On the other hand, a recess 19a for accommodating the connecting portion 18 is provided at the lower end of the CR6, and each of the engaging pieces 18 is provided at the open end of the inner peripheral surface of the recess 19a.
The bayonet type connected portion 19 is constructed by projecting four engaging protrusions 19b at intervals in the circumferential direction as shown in FIG. When the connecting portion 18 and the connected portion 19 are connected, the bottom surface of the recess 19a comes into contact with the support rod 18c, and the weight of the CR 6 is supported by the support rod 18c.

そこでCR6とCRD8との着脱は、CR6を原
子炉運転時における動作範囲よりさらに下降さ
せ、CR6の下端部をCR案内管7のシート面14
上に着座させた状態で行われる。すなわち、CR
6とCRD8との連結は、まずCR6をCR案内管
7のシート面14に着座させ、CRD8のピスト
ン16を上昇させていく。このときCRD8側の
係合片18aが第9図a,bの如く係合突起19
b間を通過するようにし、支持棒18cが凹所1
9aの底面に当接したところでCRD8を約45°回
転させて、第10図a,bの如く各係合片18a
の膨出部18bと凹所19a内の係合突起19b
とを係合させる。また、CR6とCRD8との連結
解除は、まずCR6をCR案内管7のシート面14
に着座させ、第10図a,bの状態からCRD8
を約45回転させて第9図a,bの如く各係合片1
8aの膨出部18bを凹所19a内の係合突起1
9bより外し、係合片18aが係合突起19bを
通過するようにして係合ピストン16を下降させ
ていく。
Therefore, when attaching and detaching CR6 and CRD8, CR6 is lowered further than the operating range during reactor operation, and the lower end of CR6 is attached to the seat surface 14 of CR guide tube 7.
It is performed with the person seated on top. That is, CR
6 and the CRD 8, first, the CR 6 is seated on the seat surface 14 of the CR guide tube 7, and the piston 16 of the CRD 8 is raised. At this time, the engagement piece 18a on the CRD 8 side is inserted into the engagement protrusion 19 as shown in FIGS. 9a and 9b.
b, so that the support rod 18c passes through the recess 1.
Rotate the CRD 8 by about 45 degrees when it comes into contact with the bottom surface of the CRD 9a, and then attach each engaging piece 18a as shown in FIGS. 10a and 10b.
The bulging part 18b and the engaging protrusion 19b in the recess 19a
engage with. To release the connection between CR6 and CRD8, first connect CR6 to the seat surface 14 of CR guide tube 7.
CRD8 from the states shown in Figure 10 a and b.
Rotate about 45 times to remove each engaging piece 1 as shown in Figure 9 a and b.
The bulging portion 18b of 8a is inserted into the engaging protrusion 1 in the recess 19a.
9b, and the engaging piston 16 is lowered so that the engaging piece 18a passes through the engaging protrusion 19b.

[背景技術の問題点] CRとCRDとの着脱を、相互に所定角度回転さ
せることにより可能とするBWRにおいては、CR
をCR案内管のシート面上に着座する位置まで下
降させた状態では、CRのフインガ上端部はそれ
ぞれ隣接する燃料集合体間に介在しているため、
それらの燃料集合体により回転が禁止されるが、
各フインガは薄く、しかも長さが長い(約4m)
ため、CRDとの着脱の際に下端部に回転力が作
用すると、ねじれを生じ易く、着脱時における作
業性および健全性に問題があつた。
[Problems with the background technology] In BWR, which allows the CR and CRD to be attached and detached by rotating them by a predetermined angle, the CR
When the CR fingers are lowered to a position where they are seated on the seat surface of the CR guide tube, the upper ends of the CR fingers are interposed between adjacent fuel assemblies.
Rotation is prohibited by their fuel assemblies, but
Each finger is thin and long (about 4m)
Therefore, when a rotational force is applied to the lower end portion when attaching and detaching from the CRD, twisting tends to occur, which poses problems in workability and soundness during attaching and detaching.

[発明の目的] 本発明はこのような事情にもとづいてなされた
もので、その目的は、CRとCRDとの着脱を、相
互に所定角度回転させることにより可能とする
BWRにおいて、CRとCRDとを着脱する際にCR
の下端部に回転力が作用しても、CRにねじれが
生じることのないようにし、着脱時における作業
性およびCRの健全性を向上させることにある。
[Object of the Invention] The present invention was made based on the above circumstances, and its object is to enable the attachment and detachment of CR and CRD by mutually rotating them by a predetermined angle.
In BWR, when attaching and detaching CR and CRD,
The objective is to prevent the CR from twisting even when a rotational force is applied to the lower end of the CR, thereby improving workability during attachment and detachment and the soundness of the CR.

[発明の概要] 本発明は、以上の目的達成のため、炉心に対し
挿入・引抜動作して原子炉運転時の出力制御を行
なうCRと、このCRを内部に挿通させて原子炉運
転時に昇降動作するCRに対する案内機能を有す
るとともに下端部にCRを着座させるシート面を
有するCR案内管と、前記CRの下端に連結して原
子炉運転時にはそのCRをCR案内管の内部で昇降
させ、CRの着脱はCRを前記CR案内管のシート
面に着座させた状態でCRに対し所定角度回転す
ることによつて行なうCRDと、前記CRの下端部
と前記CR案内管の下端部とに互いに上下方向よ
り凹凸嵌合可能に設けられてCRとCRDとの着脱
時におけるCRの回転を禁止する係合部および被
係合部とを具備して構成される。
[Summary of the Invention] In order to achieve the above objects, the present invention provides a CR that is inserted into and pulled out of the reactor core to control output during reactor operation, and a CR that is inserted into the inside of the reactor and used to move up and down during reactor operation. A CR guide tube has a guiding function for the operating CR and has a seat surface on the lower end for seating the CR, and is connected to the lower end of the CR to raise and lower the CR inside the CR guide tube during reactor operation. Attachment/detachment is performed by rotating the CR by a predetermined angle relative to the CR with the CR seated on the seat surface of the CR guide tube. It is configured to include an engaging portion and an engaged portion that are provided so as to be able to fit in the concave and convex portions from the direction, and prohibit rotation of the CR when the CR and the CRD are attached and detached.

[発明の実施例] 第1図ないし第4図は本発明の一実施例を示す
もので、第1図はBWRの概略構成を示す。すな
わち、冷却材(軟水)を収容する原子炉圧力容器
101の内部に炉心シユラウド102が設けら
れ、この炉心シユラウド102内に設けられた炉
心支持板103上に多数の燃料集合体104を装
荷して炉心105が構成されている。上記各燃料
集合体104は角筒状のチヤンネルボツクス内に
多数の燃料棒を収容してなるもので、平面図上に
おいては炉心シユラウド102内にマトリツクス
状になるように配列されており、原子炉圧力容器
101内の底部より上方へ向つて流通する冷却材
を核反応熱で加熱する。また炉心105には制御
棒にはCR106が配設されている。このCR10
6は中性子吸収物質を内臓した4枚のフインガを
断面が十字形となるように組合せてなるもので、
上記4枚のフインガをそれぞれ隣接する燃料集合
体104間に介在させて、4体の燃料集合体10
4に対し1体の割合で配置されている。そして各
CR106を上記燃料集合体104間に下方より
挿入することによりその挿入量に応じて炉心出力
が制御され、また各CR106を上記燃料集合体
104間より下方へ引抜くことにより炉心出力が
高められて、原子炉運転時における出力制御が行
なわれる構成となつている。
[Embodiment of the Invention] FIGS. 1 to 4 show an embodiment of the present invention, and FIG. 1 shows a schematic configuration of a BWR. That is, a core shroud 102 is provided inside a reactor pressure vessel 101 that accommodates a coolant (soft water), and a large number of fuel assemblies 104 are loaded onto a core support plate 103 provided within this core shroud 102. A reactor core 105 is configured. Each of the fuel assemblies 104 is made up of a large number of fuel rods housed in a rectangular cylindrical channel box, and in a plan view they are arranged in a matrix within the reactor core shroud 102. The coolant flowing upward from the bottom of the pressure vessel 101 is heated by nuclear reaction heat. Further, a CR 106 is disposed in the control rod of the reactor core 105. This CR10
6 is made by combining four fingers containing a neutron absorbing substance so that the cross section is cross-shaped.
The four fingers are interposed between adjacent fuel assemblies 104 to form four fuel assemblies 10.
They are arranged at a ratio of 1 to 4. and each
By inserting the CR 106 from below between the fuel assemblies 104, the core output is controlled according to the insertion amount, and by pulling each CR 106 downward from between the fuel assemblies 104, the core output is increased. The structure is such that output control is performed during reactor operation.

また図中107は上記炉心105の下方に各
CR106ごとに対応して設けられた円筒形状の
CR案内管で、このCR案内管107は各CR10
6を内部に挿通させ、原子炉通常運転時に昇降動
作するCR106の案内をするものである。そし
て原子炉圧力容器101の下方にはCR106を
昇降駆動するCRD108が設けられている。
In addition, 107 in the figure indicates each area below the core 105.
Cylindrical shape corresponding to each CR106
This CR guide tube 107 is for each CR10
6 is inserted into the interior to guide the CR 106 which moves up and down during normal reactor operation. A CRD 108 is provided below the reactor pressure vessel 101 to drive the CR 106 up and down.

前記炉心シユラウド102の上端はシユラウド
ヘツド109で閉塞されており、このシユラウド
ヘツド109上には気水分離器110が接続され
ている。この気水分離器110は炉心105で加
熱されて蒸発した冷却材蒸気を気水分離するもの
であり、さらに気水分離器110上には、気水分
離された蒸気を乾燥させる蒸気乾燥器111が接
続されている。そして蒸気乾燥器111を通過し
た蒸気は、図示しない主蒸気管を通して原子炉容
器101外の発電機駆動用タービンへ送出され
る。
The upper end of the core shroud 102 is closed with a shroud head 109, and a steam separator 110 is connected above the shroud head 109. This steam-water separator 110 separates the coolant vapor heated and evaporated in the core 105 into steam and water, and further above the steam-water separator 110 is a steam dryer 111 for drying the separated steam. is connected. The steam that has passed through the steam dryer 111 is sent to a generator-driving turbine outside the reactor vessel 101 through a main steam pipe (not shown).

前記CR案内管107は、炉心支持板103を
貫通しその上端外周部を炉心支持板103に懸架
され、さらにその上端部を炉心支持板103の上
面側に突設されたピンに係合させてその回転が禁
止されている。また各CR案内管107の上端四
隅部には、それぞれ燃料集合体104を下方より
支持する燃料サポートが形成されている。さらに
CR案内管107の内周面下端部には第2図に示
す如くCR106の下端部を着座させるシート面
112が設けられている。また、CR案内管10
7の下端部には係止部113が設けられている。
The CR guide tube 107 penetrates through the core support plate 103, has its upper end outer periphery suspended by the core support plate 103, and has its upper end engaged with a pin protruding from the upper surface side of the core support plate 103. Its rotation is prohibited. Furthermore, fuel supports are formed at the four corners of the upper end of each CR guide tube 107 to support the fuel assembly 104 from below. moreover
A seat surface 112 is provided at the lower end of the inner peripheral surface of the CR guide tube 107, as shown in FIG. 2, on which the lower end of the CR 106 is seated. In addition, CR guide tube 10
A locking portion 113 is provided at the lower end portion of 7.

前記CRD108は原子炉圧力容器101の底
部鏡板101aを貫通してこの底部鏡板101a
に溶接された円筒形状のCRDハウジング114
に収容支持されている。そしてこのCRDハウジ
ング114内に、前記CR案内管107の係止部
113を上方より導入させている。
The CRD 108 passes through the bottom head plate 101a of the reactor pressure vessel 101 and is connected to the bottom head plate 101a.
Cylindrical CRD housing 114 welded to
It is supported by accommodation. The locking portion 113 of the CR guide tube 107 is introduced into the CRD housing 114 from above.

CRD108は前記CRDハウジング114の内
周に嵌合すアウターチユーブ115の上端に被係
止部116を有し、この被係止部1166前記
CR案内管107の係止部113とで互いに係脱
自在なバヨネツト連結機構が構成されている。そ
してさらにCRD108は上記アウターチユーブ
115内を昇降動作するピストン117、このピ
ストン117を昇降駆動するモータ部118(第
1図参照)を有し、モータ118をCRDハウジ
ング114の下方に露出させた状態で、CRDハ
ウジング114の下端フランジ部にボルト等によ
り取りつけられている。
The CRD 108 has a locked portion 116 at the upper end of an outer tube 115 that fits into the inner periphery of the CRD housing 114.
The locking portion 113 of the CR guide tube 107 constitutes a bayonet connection mechanism that can be freely engaged and detached from each other. The CRD 108 further includes a piston 117 that moves up and down within the outer tube 115, and a motor section 118 (see FIG. 1) that drives the piston 117 up and down. , is attached to the lower end flange portion of the CRD housing 114 with bolts or the like.

前記CRD108のピストン117上端には、
周方向等間隔に配置された4本のたて長な係合片
119aよりなるバヨネツト式連結部119が設
けられ、各係合片119aの外面先端部には膨出
部119bが形成されている。さらに、上記4本
の係合片119aの中央には支持棒119cが上
方向へ向つて突設され、この支持棒119cで4
本の係合片119aの内方へのたわみ量を制限す
るようにしている。一方、CR106の下端には
上記連結部119を収容する凹所120aが設け
られ、その凹所120aの内周面開口端部には上
記各係合片119aに対応するように4つの係合
突起120bを周方向間隔に突出させてバヨネツ
ト式被連結部120が構成されている。そして上
記連結部119と被連結部120とが連結された
状態では凹所120aの底面が支持棒119cに
当接し、CR106の重量が支持棒119cによ
つて支持されるようになる。
At the upper end of the piston 117 of the CRD 108,
A bayonet type connecting portion 119 is provided which is made up of four vertically elongated engaging pieces 119a arranged at equal intervals in the circumferential direction, and a bulging portion 119b is formed at the tip of the outer surface of each engaging piece 119a. . Furthermore, a support rod 119c is provided in the center of the four engaging pieces 119a to protrude upward, and this support rod 119c
The amount of inward deflection of the book engagement piece 119a is limited. On the other hand, a recess 120a for accommodating the connecting portion 119 is provided at the lower end of the CR 106, and four engaging protrusions are provided at the open end of the inner peripheral surface of the recess 120a to correspond to each of the engaging pieces 119a. The bayonet type connected portion 120 is configured by projecting the portions 120b at intervals in the circumferential direction. When the connecting portion 119 and the connected portion 120 are connected, the bottom surface of the recess 120a comes into contact with the support rod 119c, and the weight of the CR 106 is supported by the support rod 119c.

前記CR106の下端外周部には、第2図ない
し第4図に示す如く、1または複数の凸部(図で
は2つの凸部を設けた例を示す)よりなる係合部
121が突設されている。一方、前記CR密内管
107の下部には、CR106の上記係合部12
1が設けられている箇所を囲む位置に円筒部12
2が設けられ、この円筒部122の内周面には上
記係合部121の各凸部と対応する、凸部と同数
の凹部よりなる被係合部123が設けられてい
る。そしてこれら係合部121と被係合部123
とは、第2図の如くCR106をCR案内管107
のシート面112に着座する位置まで下降させる
とき互いに上下方向より凹凸嵌合する関係にあ
る。
As shown in FIGS. 2 to 4, an engaging portion 121 consisting of one or more convex portions (the figure shows an example with two convex portions) is provided on the outer peripheral portion of the lower end of the CR 106. ing. On the other hand, at the lower part of the CR inner tube 107, the engaging portion 12 of the CR 106 is provided.
A cylindrical portion 12 is located at a position surrounding the location where 1 is provided.
2, and on the inner circumferential surface of this cylindrical portion 122, an engaged portion 123 consisting of the same number of concave portions as the convex portions and corresponding to each convex portion of the engaging portion 121 is provided. These engaging portions 121 and engaged portions 123
means that the CR106 is connected to the CR guide pipe 107 as shown in Figure 2.
When lowered to a position where they are seated on the seat surface 112, they are in a relationship in which they fit into each other from above and below.

そこでCR106とCRD108との着脱は、
CR106を原子炉運転時における動作範囲より
さらに下降させ、CR106の下端部をCRD案内
管107のシート面112上に着座させた状態で
行われる。すなわち、CR106とCRD108と
の連結は、まずCR106をCR案内管107のシ
ート面112に着座させ、CRD108のピスト
ン117を上昇させていく。このときCRD10
8側の係合片119aが係合突起120b間を通
過するようにし、支持棒119cが凹所120a
の底面に当接したところでCRD108を約45°回
転させて、各係合片119aの膨出部119bと
凹所120a内の係合突起120bとを係合させ
る。また、CR106とCRD108との連結解除
は、まずCR106をCR案内管107のシート面
112に着座させ、CRD108を約45℃回転さ
せて各係合片119aの膨出部119bを凹所1
20a内の係合突起120bより外し、係合片1
19aが係合突起120b間を通過するようにし
て係合ピストン117を下降させていく。
Therefore, to attach and detach CR106 and CRD108,
This is carried out with the CR 106 lowered further than the operating range during reactor operation and with the lower end of the CR 106 seated on the seat surface 112 of the CRD guide tube 107. That is, to connect the CR 106 and the CRD 108, first the CR 106 is seated on the seat surface 112 of the CR guide tube 107, and the piston 117 of the CRD 108 is raised. At this time CRD10
The engagement piece 119a on the 8th side passes between the engagement protrusions 120b, and the support rod 119c is inserted into the recess 120a.
When the CRD 108 comes into contact with the bottom surface of the CRD 108, the CRD 108 is rotated approximately 45 degrees to engage the bulging portion 119b of each engagement piece 119a with the engagement protrusion 120b in the recess 120a. To disconnect the CR 106 and CRD 108, first seat the CR 106 on the seat surface 112 of the CR guide tube 107, rotate the CRD 108 by about 45 degrees, and align the bulge 119b of each engagement piece 119a with the recess.
20a from the engagement protrusion 120b, and remove the engagement piece 1.
The engagement piston 117 is lowered so that the engagement piston 19a passes between the engagement protrusions 120b.

そしてこのようにしてCR106とCRD108
との着脱を行なう際、CR106の下端部は係合
部121と被係合部123との係合により回転を
禁止されているので、CRD108をCR106に
対して回転させた場合でもCR106の下端部が
CRD108に追随して回転することはなく、ね
じれ等を生じることはない。したがつて、CR1
06とCRD108との着脱時における作業性が
改善され、CR106の健全性も向上することに
なる。
And in this way CR106 and CRD108
When attaching and detaching the CR 106, the lower end of the CR 106 is prohibited from rotating due to the engagement between the engaging portion 121 and the engaged portion 123, so even if the CRD 108 is rotated relative to the CR 106, the lower end of the but
It does not rotate following the CRD 108 and does not cause twisting or the like. Therefore, CR1
The workability when attaching and detaching the CRD 108 to the CRD 108 is improved, and the soundness of the CR 106 is also improved.

なお、上記実施例ではCR106側の係合部1
21を凸部とし、CRD108側の被係合部12
3を凹部としたが、凸部と凹部とを逆の関係にし
てもよい。また、それら凸部および凹部の数も任
意に設定可能である。
In addition, in the above embodiment, the engaging portion 1 on the CR106 side
21 is a convex portion, and the engaged portion 12 on the CRD 108 side
Although 3 is a recessed portion, the relationship between the protruding portion and the recessed portion may be reversed. Further, the number of these convex portions and concave portions can also be set arbitrarily.

[発明の効果] 以上詳述したように、本発明のBWRによれ
ば、CRの下端部とCR案内管の上端部とに互いに
上下方向より凹凸嵌合可能に設けられてCRと
CRDとの着脱時におけるCRの回転を禁止する係
合部および被係合部とを設けたことにより、CR
とCRDとを着脱する際にCRの下端部に回転力が
作用しても、CRにねじれが生じることがなく、
着脱時における作業性およびCRの健全性の向上
を図ることができる。
[Effects of the Invention] As detailed above, according to the BWR of the present invention, the lower end of the CR and the upper end of the CR guide tube are provided so that the CR and the CR guide tube can be engaged with each other from above and below.
CR
Even if rotational force is applied to the lower end of the CR when attaching and detaching the CR and the CRD, the CR will not be twisted.
It is possible to improve workability during attachment and detachment and the soundness of the CR.

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

第1図ないし第4図は本発明の一実施例を示す
もので、第1図はBWRの概略構成を示す断面
図、第2図はCR案内管とCRDとの接続部周辺の
断面図、第3図は第2図の−断面図、第4図
はCRの係合部とCR案内管の被係合部との関係を
示す斜視図、第5図ないし第10図は背景技術を
説明するもので、第5図はBWRの概略構成を示
す断面図、第6図は第8図の−断面図、第7
図は第8図の−断面図、第9図aはCRと
CRDとの連結解除状態を示す断面図、同図bは
同図aの−断面図、第10図aはCRとCRD
との連結状態を示す断面図、同図bは同図aの
−断面図である。 105……炉心、106……CR(制御棒)、1
07……CR案内管(制御棒)、108……CRD
(制御棒駆動機構)、112……シート面、121
……係合部、123……被係合部。
Figures 1 to 4 show an embodiment of the present invention, in which Figure 1 is a cross-sectional view showing the schematic configuration of a BWR, Figure 2 is a cross-sectional view of the area around the connection between the CR guide pipe and the CRD, Fig. 3 is a cross-sectional view of Fig. 2, Fig. 4 is a perspective view showing the relationship between the engaging part of the CR and the engaged part of the CR guide tube, and Figs. 5 to 10 explain the background art. Figure 5 is a cross-sectional view showing the schematic configuration of the BWR, Figure 6 is a cross-sectional view of Figure 8, and Figure 7 is a cross-sectional view showing the schematic configuration of the BWR.
The figure is a cross-sectional view of Fig. 8, and Fig. 9 a is a cross-sectional view of CR.
A cross-sectional view showing the disconnected state from the CRD, Figure b is a - cross-sectional view of Figure a, Figure 10 a is the CR and CRD
Figure b is a cross-sectional view taken from figure a. 105...Reactor core, 106...CR (control rod), 1
07...CR guide tube (control rod), 108...CRD
(control rod drive mechanism), 112... seat surface, 121
...Engaging part, 123...Engaged part.

Claims (1)

【特許請求の範囲】 1 炉心に対し挿入・引抜動作して原子炉運転時
の出力制御を行なう制御棒と、この制御棒を内部
に挿通させて原子炉運転時に昇降動作する制御棒
に対する案内機能を有するとともに下端部に制御
棒を着座させるシート面を有する制御棒案内管
と、前記制御棒の下端に連結して原子炉運転時に
はその制御棒を制御棒案内管の内部で昇降させ、
制御棒に対する着脱は制御棒を前記制御棒案内管
のシート面に着座させた状態で制御棒に対し所定
角度回転することによつて行なう制御棒駆動機構
と、前記制御棒の下端部と前記制御棒案内管の下
端部とに互いに上下方向より凹凸嵌合可能に設け
られて制御棒と制御棒駆動機構との着脱時におけ
る制御棒の回転を禁止する係合部および被係合部
とを具備したことを特徴とする沸騰水型原子炉。 2 前記制御棒の外周下端部に凸部を設けて前記
係合部とし、前記制御棒案内管の上端部に凹部を
設けて前記被係合部とした特許請求の範囲第1項
記載の沸騰水型原子炉。
[Scope of Claims] 1. A control rod that is inserted into and pulled out of the reactor core to control output during reactor operation, and a guide function for the control rod that is inserted into the core and moves up and down during reactor operation. and a control rod guide tube having a seat surface on which a control rod is seated at its lower end; and a control rod guide tube connected to the lower end of the control rod so that the control rod is raised and lowered inside the control rod guide tube during reactor operation;
The control rod is attached to and detached from the control rod by rotating the control rod at a predetermined angle with respect to the control rod while seated on the seat surface of the control rod guide tube. The lower end of the rod guide tube is provided with an engaging part and an engaged part that are provided so as to be able to engage with each other in a concave and convex manner from above and below, and that prohibit rotation of the control rod when the control rod and the control rod drive mechanism are attached or detached. A boiling water reactor characterized by: 2. The boiling point according to claim 1, wherein a convex portion is provided at the lower end of the outer periphery of the control rod to serve as the engaging portion, and a concave portion is provided at the upper end of the control rod guide tube to serve as the engaged portion. Water reactor.
JP59124688A 1984-06-18 1984-06-18 Boiling-water type reactor Granted JPS613084A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59124688A JPS613084A (en) 1984-06-18 1984-06-18 Boiling-water type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59124688A JPS613084A (en) 1984-06-18 1984-06-18 Boiling-water type reactor

Publications (2)

Publication Number Publication Date
JPS613084A JPS613084A (en) 1986-01-09
JPH0476076B2 true JPH0476076B2 (en) 1992-12-02

Family

ID=14891618

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59124688A Granted JPS613084A (en) 1984-06-18 1984-06-18 Boiling-water type reactor

Country Status (1)

Country Link
JP (1) JPS613084A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE102011108802B4 (en) * 2011-07-29 2013-02-21 Areva Np Gmbh Connection between control rod guide tube and drive housing tube of a nuclear reactor

Also Published As

Publication number Publication date
JPS613084A (en) 1986-01-09

Similar Documents

Publication Publication Date Title
US10878970B2 (en) Nuclear reactor refueling methods and apparatuses
US7085340B2 (en) Nuclear reactor fuel assemblies
US20080084957A1 (en) Nuclear reactor fuel assemblies
EP2146350B1 (en) Nuclear fuel assembly with a lock-support spacer grid
US4980121A (en) Protective device for lower end portion of a nuclear fuel rod cladding
US4904443A (en) Control rod drive with upward removable drive internals
US6934350B1 (en) Core configuration for a nuclear reactor
JPS6133477B2 (en)
US4744942A (en) Nuclear reactor spacer grid loading
JPH0476076B2 (en)
JPS62261989A (en) Integral locking device for upper nozzle
US4100021A (en) Nuclear reactor vessel and internals alignment apparatus
JPS62159090A (en) Control rod for nuclear reactor
JPH0476077B2 (en)
KR910005731B1 (en) Fuel assembly for a nuclear reactor
US5133926A (en) Extended burnup top nozzle for a nuclear fuel assembly
EP0773553B1 (en) Fuel assembly structure selectively using channel and coolant rod for load support and method of lifting the fuel assembly
US4709909A (en) Retention strap in a grid assembly fixture
US4142935A (en) Nuclear reactor
EP0768677B1 (en) Fuel assembly structure using channel for load support and method for removing a fuel bundle from the channel
JPH05196767A (en) Double-enclusure-wall type upper nozzle assembly for nuclear fuel assembly
JPS59102190A (en) Control rod drive mechanism
JPS63149593A (en) Control rod assembly
JP2022065354A (en) Boiling water reactor and fuel assemblies
JPS6045392B2 (en) boiling water reactor