JPH0476077B2 - - Google Patents

Info

Publication number
JPH0476077B2
JPH0476077B2 JP59168979A JP16897984A JPH0476077B2 JP H0476077 B2 JPH0476077 B2 JP H0476077B2 JP 59168979 A JP59168979 A JP 59168979A JP 16897984 A JP16897984 A JP 16897984A JP H0476077 B2 JPH0476077 B2 JP H0476077B2
Authority
JP
Japan
Prior art keywords
crd
control rod
guide tube
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
JP59168979A
Other languages
Japanese (ja)
Other versions
JPS6147586A (en
Inventor
Mitsuharu Nakamura
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 JP59168979A priority Critical patent/JPS6147586A/en
Publication of JPS6147586A publication Critical patent/JPS6147586A/en
Publication of JPH0476077B2 publication Critical patent/JPH0476077B2/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)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (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連結を
バヨネツト機構で行なう沸騰水型原子炉(一般に
ABWRと称せられる)に係り、特に制御棒と制
御棒駆動機構との着脱を、制御棒または制御棒駆
動機構のいずれの側からでも行なえるようにした
沸騰水型原子炉(以下BWRと称する)に関す
る。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a boiling water reactor (generally known as
In particular, boiling water reactors (hereinafter referred to as BWRs) are capable of attaching and detaching control rods and control rod drive mechanisms from either side of the control rods or control rod drive mechanism. Regarding.

[発明の技術的背景] BWRは、第4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5図
および第6図に示す如く中性子吸収物質を内蔵し
た4枚のブレード6aを断面が十字形となるよう
に組合せ、下端にはソケツト6aを有するもの
で、上記4枚のブレード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抑制さ
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 4.
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. 5 and 6, this CR6 has four blades 6a containing a neutron absorbing material assembled in a cross-shaped cross section, and has a socket 6a at the lower end. The blades 6a are interposed between adjacent fuel assemblies 4, and are arranged at a ratio of one for every four fuel assemblies 4. and each
By inserting the CR6 between the fuel assemblies 4 from below, the core output is suppressed according to the amount of insertion, and by pulling out each CR6 downward from between the fuel assemblies 4, the core output is increased. The structure is such that output control is performed during reactor operation.

また第4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6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 Figure 4 indicates each CR6 below the core 5.
A cylindrical control rod guide tube (hereinafter referred to as CR guide tube) is provided correspondingly 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、こ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7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、CR案
内管7の内周面のほぼ中間高さ位置にはCR6の
ブレード6aと係合してCR6の回転を禁止する
回り止め部7aが設けられている。
As shown in FIG. 7, 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 circumferential surface of the CR guide tube 7 on which the lower end of the CR 6 is seated, and at a substantially mid-height position on the inner circumferential surface of the CR guide tube 7, the seat surface 14 engages with the blade 6a of the CR6. A rotation preventing portion 7a is provided to prevent rotation of CR6.

前記CRD8は第7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の下方に位置させた状態で、
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.
While positioned below the CRD housing 15,
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。特にバヨネツト機構を採用したものは
ABWR(AdvanceBWR)と称されており、第8
図a,bおよび第9図a,bにその具体的構造を
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1
8b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1
8aの内方へのたわみ量を制限するようにしてい
る。一方、CR6下端のソケツト6b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1
8aに対応するように4つの係合突起19bを周
方向等間隔に突出させてバヨネツト式被連結部1
9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. Especially those that use a bayonet mechanism.
It is called ABWR (Advance BWR) and is the 8th
The specific structure is shown in Figures a and b and Figures 9a and b. 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 elongated engaging pieces 18a arranged at equal intervals in the circumferential direction, and the outer end of each engaging piece 18a is provided with a bayonet type connecting portion 18. Bulging part 1
8b is formed. Further, a support rod 18c is provided at the center of the four engagement pieces 18a to protrude upward, and this support rod 18c is used to connect the four engagement pieces 18a to the center.
The amount of inward deflection of 8a is limited. On the other hand, a recess 19a for accommodating the connecting portion 18 is provided in the socket 6b at the lower end of the CR6, and each of the engaging pieces 1 is provided at the open end of the inner peripheral surface of the recess 19a.
8a, four engaging protrusions 19b are protruded at equal intervals in the circumferential direction to form the bayonet type connected portion 1.
9 are configured. 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8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9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。このとき、CR6の回転はCR6の
各ブレード6aと回り止め部7aとの係合により
禁止される。また、CR6とCRD8との離脱は、
まずCR6をCR案内管7のシート面14に着座さ
せ、第9図a,bの状態からCRD8を約45゜回転
させて第8図a,bの如く各係合片18aの膨出
部18bを凹所19a内の係合突起19bより外
し、係合片18aが係合突起19b間の通過する
ようにして係合ピストン16を下降させていく。
なお、離脱操作を行なう場合にもCR6は各ブレ
ード6aと回り止め部7aとの係合により回転を
禁止されることになる。
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 engages the engagement protrusion 19 as shown in Fig. 8a and b.
b, so that the support rod 18c passes through the recess 1.
When it comes into contact with the bottom surface of the CRD 9a, rotate the CRD 8 by about 45 degrees to engage the protrusion 18b of each engagement piece 18a with the engagement protrusion 19b in the recess 19a, as shown in FIGS. 9a and 9b. . At this time, rotation of the CR6 is prohibited by engagement between each blade 6a of the CR6 and the rotation stopper 7a. Also, the separation from CR6 and CRD8 is
First, the CR 6 is seated on the seat surface 14 of the CR guide tube 7, and the CRD 8 is rotated approximately 45 degrees from the state shown in FIGS. is removed from the engagement protrusion 19b in the recess 19a, and the engagement piston 16 is lowered so that the engagement piece 18a passes between the engagement protrusions 19b.
Note that even when performing a detachment operation, the CR 6 is prohibited from rotating due to the engagement between each blade 6a and the rotation stopper 7a.

[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従来のBWRでは、CR
の回転はCR案内管のほぼ中間高さ位置に設けら
れた回り止め部により禁止されているため、両者
の着脱は専らCRDを回転させることによつて行
なわれる。このためCRのみを取出す場合でもそ
の都度CRDをCRDハウジングから取外さねばな
らなかつた。このため、CRDの取外しに長時間
を要し、ペデスタル内での作業時間が長時間に及
ぶため作業員の被曝線量が増加するという問題が
あつた。なお、CRDを取外すことなくCRの方を
回転させて離脱を行なうことも考えられる。とこ
ろが、CRを回転させるためにはこれを回り止め
部よりも上方までCRDのピストンによつて上昇
させた状態で行なわねばならず、回り止め部がか
なり高い位置にあることからCRDのピストンが
傾いてしまい、そのような状態で両者の離脱を行
なうことは実際上、きわめて困難であつた。
[Problems with the background technology] In the conventional BWR, the CR and CRD can be attached and detached by mutually rotating them at a predetermined angle.
Since rotation of the CRD is prohibited by a rotation stopper provided at approximately the mid-height position of the CR guide tube, attachment and detachment of both is performed exclusively by rotating the CRD. For this reason, even if only the CR was to be removed, the CRD had to be removed from the CRD housing each time. For this reason, it took a long time to remove the CRD, and the amount of time workers spent working inside the pedestal increased, resulting in an increased radiation dose for workers. It is also conceivable to rotate the CR and remove it without removing the CRD. However, in order to rotate the CR, the piston of the CRD must be raised above the detent, and since the detent is located at a fairly high position, the CRD piston is tilted. In reality, it would have been extremely difficult for the two parties to separate in such a situation.

[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との着脱をCRまたは
CRDのいずれの側からでも行なうことができ、
特にCRの取外し作業はCRDをCRハウジングよ
り取外すことなく短時間で行なえるようにして作
業員の被曝線量の大幅低減を図ることにある。
[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 the CR and CRD by mutually rotating them by a predetermined angle.
In BWR, attaching and detaching CR and CRD is done by CR or
Can be done from either side of the CRD,
In particular, the aim is to significantly reduce the radiation exposure of workers by making it possible to remove the CR in a short time without removing the CRD from the CR housing.

[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との着脱はCRに対し所定感度回転するこ
とによつて行なうCRDと、前記CRD案内管の下
端部に設けられ前記の下端部を上方より嵌合させ
てCRの回転を禁止する回り止め部とを具備して
達成される。
[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 having a guiding function for the operating CR is connected to the lower end of the CR, and during reactor operation, the CR is raised and lowered inside the CR guide tube, and the attachment and detachment from the CR is performed by rotating with a predetermined sensitivity to the CR. This is achieved by comprising a CRD that is performed by the CRD, and a rotation stopper that is provided at the lower end of the CRD guide tube and engages the lower end from above to prevent rotation of the CR.

[発明の実施例] 第1図ないし第3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の内部には炉心シユラウド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は各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1
01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CR1
06が配設されている。このCR106は中性子
吸収物質を内蔵した4枚のブレード106aを断
面が十字形となるように組合せ、下端にソケツト
106b(第2図参照)を有するもので、上記4
枚のブレード106a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1
04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
力が抑制され、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 3 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 each cylindrical channel box, and is arranged in a matrix in the reactor core shroud 102 in a plan view. container 1
The coolant flowing upward from the bottom of 01 is heated by nuclear reaction heat. In addition, CR1 is installed in the core 105.
06 is installed. This CR106 combines four blades 106a containing a neutron absorbing material so that the cross section is cross-shaped, and has a socket 106b (see Figure 2) at the lower end.
The four fuel assemblies 1 are interposed between the adjacent fuel assemblies 104 with the blades 106 a
They are placed at a ratio of 1 to 04. By inserting each CR 106 from below between the fuel assemblies 104, the core output is suppressed according to the insertion amount, and by withdrawing each CR 106 from below between the fuel assemblies 104, the core output is increased. The configuration 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発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 evaporated coolant 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
貫通して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1
07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 and has its upper end outer periphery suspended by the core support plate 103, and its upper end is 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. Furthermore, 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. Also, CR guide tube 1
A locking portion 113 is provided at the lower end portion of 07.

また第1図および第2図に示すように、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1
14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。
In addition, as shown in FIGS. 1 and 2,
The CRD 108 is housed and supported in a cylindrical CRD housing 114 that passes through the bottom end plate 101a of the reactor pressure vessel 101 and is welded to the bottom end plate 101a. And this CRD housing 1
14 includes a locking portion 113 of the CR guide tube 107.
is being introduced from above.

CRD108は前記CRDハウジング114の内
周に嵌合するアウターチユーブ115の上端に被
係止部116を有し、この被係止部116と前記
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、モータ部118部をCRDハウ
ジング114の下方に位置させた状態で、CRD
ハウジング114の下端フランジ部にボルト等に
より取付けられている。
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. Furthermore, the CRD 108 includes a piston 117 that moves the outer tube 115 up and down, and a motor section 118 (first
), and with the motor section 118 located below the CRD housing 114, the CRD
It is attached to the lower end flange portion of the housing 114 with bolts or the like.

前記CRD108のピストン117上端には、
周方向間隔に配置された4本のたて長な係合片1
19a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下端のソケツ
ト106b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を周方向等間隔に突
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12
0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,
Four vertically long engagement pieces 1 arranged at intervals in the circumferential direction
A bayonet type connecting portion 119 consisting of 19a is provided, and a bulging portion 119b is formed at the tip of the outer surface of each engaging piece 119a. Further, a support rod 119c is provided at the center of the four engagement pieces 119a to project upward, and this support rod 119c limits the amount of inward deflection of the four engagement pieces 119a. I have to. On the other hand, the socket 106b at the lower end of the CR 106 is provided with a recess 120a for accommodating the connecting portion 119, and the opening end of the inner peripheral surface of the recess 120a has four engaging pieces corresponding to the respective engaging pieces 119a. The bayonet type connected portion 120 is constructed by projecting mating projections 120b at equal intervals in the circumferential direction. The connecting portion 119 and the connected portion 12
0 is 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CR案内管107内の下端部には、CR10
6の各ブレード106aの下端部を上方より嵌合
させる回り止め部122が設けられている。この
回り止め部122は円筒体の上部に4つの嵌合溝
123を等間隔に形成した構成のもので、各嵌合
溝123はCR106のブレード106aを嵌合
させ得る幅寸法を有し、各嵌合溝123の両内面
上半部にはブレード106aを上方より嵌合させ
る際のガイドとなる傾斜面123aが形成されて
いる。そしてCR106の各ブレード106aと
嵌合溝123とは、第2図の如くCR106のソ
ケツト106bをCR案内管107のシート面1
12に着座する位置まで下降させた状態で互いに
上下方向より凹凸嵌合する関係にある。
At the lower end of the CR guide tube 107, a CR10
A rotation preventing portion 122 is provided into which the lower end portion of each blade 106a of No. 6 is fitted from above. This rotation prevention part 122 has a structure in which four fitting grooves 123 are formed at equal intervals in the upper part of a cylindrical body. An inclined surface 123a is formed in the upper half of both inner surfaces of the fitting groove 123 to serve as a guide when fitting the blade 106a from above. As shown in FIG.
12, they are in a relationship in which they fit into each other in a concave and convex manner from above and below.

そこでCR106とCRD108との着脱は、次
の2通りの方法で行なうことができる。
Therefore, the CR 106 and CRD 108 can be attached and detached using the following two methods.

まず第1の方法は、CRD108を回転する方
法である。これは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(ソケツト106b)をCRD案内管10
7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11
7を上昇させていく。このときCRD108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全体を約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、
CRD108をCRDハウジング114にボルトに
よつて取付ける。また、CR106とCRD108
との離脱は、まずCR106をCR案内管107の
シート面112に着座させ、CRD108のCRD
ハウジング114に対する取付けボルトを外し、
CRD108全体を約45゜回転させて各係合片11
9aの膨出部119bを凹所120a内の係合突
起120bより外し、係合片119aが係合突起
120b間を通過するようにして係合ピストン1
17を下降させていく。
The first method is to rotate the CRD 108. This lowers the CR106 further below the operating range during reactor operation, and lowers the lower end of the CR106 (socket 106b) to the CRD guide pipe 10.
This is done with the person seated on the seat surface 112 of No. 7. 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 then the piston 11 of the CRD 108 is connected.
7 will rise. At this time, the engagement piece 119a on the CRD 108 side is made to pass between the engagement protrusions 120b, and when the support rod 119c comes into contact with the bottom surface of the recess 120a, the entire CRD 108 is rotated about 45 degrees, and each engagement piece 119a engaging the protrusion 119b and the engagement protrusion 120b in the recess 120a;
Attach CRD 108 to CRD housing 114 with bolts. Also, CR106 and CRD108
To remove the CR106, first seat the CR106 on the seat surface 112 of the CR guide tube 107, and then
Remove the mounting bolts for the housing 114,
Rotate the entire CRD 108 by approximately 45 degrees and attach each engaging piece 11.
9a is removed from the engagement protrusion 120b in the recess 120a, and the engagement piston 1 is moved so that the engagement piece 119a passes between the engagement protrusions 120b.
17 will be lowered.

そしてこのようにしてCR106とCRD108
との着脱を行なう際、CR106はブレード10
6aの下端部と回り止め部122の嵌合溝123
との係合により回転を禁止されているので、
CRD108をCR106に対して容易に回転させ
ることができる。
And in this way CR106 and CRD108
When attaching and detaching the CR106 to the blade 10
Fitting groove 123 between the lower end of 6a and the rotation stopper 122
Rotation is prohibited due to engagement with
CRD 108 can be easily rotated relative to CR 106.

次に第2の方法はCR106の方を回転する方
法で、CRD108は残してCR106のみ取外す
必要がある場合に特に有効である。これはCRD
108のピストン117によりCR106を最下
位置よりわずかに上昇させてCR106のブレー
ド106b下端部を回り止め部122の嵌合溝1
23より離脱させた状態で行われる。すなわち、
まずCR106をCRD108のピストン117に
よつてわずかに上昇させ、CR106のブレード
106b下端部を回り止め部122の嵌合溝12
3より離脱させた状態でCR106の方を約45゜回
転させて、各係合片119aの膨出部119bか
ら凹所120a内の係合突起120bを離脱さ
せ、そのままCR106を上方へ吊上げるのであ
る。この場合はCRD108のピストン117が
CRDハウジング114内で回転を禁止されてい
るため、CR106の回転操作は容易に行なえる。
The second method is to rotate the CR 106, which is particularly effective when only the CR 106 needs to be removed while leaving the CRD 108 behind. This is CRD
The CR 106 is slightly raised from the lowest position by the piston 117 of 108, and the lower end of the blade 106b of the CR 106 is inserted into the fitting groove 1 of the rotation stopper 122.
It is carried out in a state where it is separated from 23. That is,
First, the CR 106 is slightly raised by the piston 117 of the CRD 108, and the lower end of the blade 106b of the CR 106 is inserted into the fitting groove 12 of the rotation stopper 122.
3, rotate the CR 106 by about 45 degrees to disengage the engagement protrusion 120b in the recess 120a from the bulge 119b of each engagement piece 119a, and then lift the CR 106 upward. be. In this case, the piston 117 of CRD108
Since rotation is prohibited within the CRD housing 114, rotation of the CR 106 can be easily performed.

したがつて、以上の構成では、CR106と
CRD108との着脱をCR106またはCRD10
8のいずれの側からでも行なうことができ、特に
CR106の取外し作業はCRD108をCRハウ
ジング114より取外すことなく短時間で行なう
ことができるので、作業員の被曝線量の大幅低減
を図ることができる。
Therefore, in the above configuration, CR106 and
Attaching and detaching from CRD108 to CR106 or CRD10
It can be done from either side of the 8, especially
Since the removal work of the CR 106 can be carried out in a short time without removing the CRD 108 from the CR housing 114, it is possible to significantly reduce the radiation dose to the workers.

[発明の効果] 以上詳述したように、本発明によれば、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
の着脱をCRまたはCRDのいずれの側からでも行
なうことができ、特にCRの取外し作業はCRDを
CRハウジングより取外すことなく短時間で行な
うことができ、作業員の被曝線量の大幅低減を図
ることができる。
[Effect of the invention] As detailed above, according to the present invention, CR and
In BWRs, which can be attached and detached from the CRD by rotating them by a predetermined angle, the CR and CRD can be attached and detached from either the CR or the CRD.
This can be done in a short time without removing it from the CR housing, significantly reducing the radiation dose to workers.

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

第1図ないし第3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−矢視図、第4図
ないし第9図は従来例を示すもので、第4図は
BWRの概略構成を示す断面図、第5図は第7図
の−断面図、第6図は第7図の−断面
図、第8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9
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
06a……ブレード、106b……ソケツト、1
07……CR案内管(制御棒案内管)、108……
CRD(制御棒駆動機構)、122……回り止め部、
123……嵌合溝。
Figures 1 to 3 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 view taken in the direction of - arrow in Fig. 2, Figs. 4 to 9 show conventional examples, and Fig. 4 shows a conventional example.
5 is a cross-sectional view showing the schematic configuration of BWR, FIG. 5 is a cross-sectional view of FIG. 7, FIG. 6 is a cross-sectional view of FIG. 7, and FIG. , Figure b is a cross-sectional view of Figure a, No. 9
Figure a is a sectional view showing the connection state of CR and CRD, and figure b is a cross-sectional view taken from figure a. 105...Reactor core, 106...CR (control rod), 1
06a...Blade, 106b...Socket, 1
07...CR guide tube (control rod guide tube), 108...
CRD (control rod drive mechanism), 122... rotation stopper,
123... Fitting groove.

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制御案内管と、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、制御棒との
着脱は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、前記制御棒案内管の
下端部に設けられ、前記制御棒の下端部を上方よ
り嵌合させて制御棒の回転を禁止する回り止め部
とを具備したことを特徴とする沸騰水型原子炉。 2 前記回り止め部は制御棒の4枚のブレードの
下端部をそれぞれ嵌合させる4つの嵌合溝を有す
ることを特徴とする特許請求の範囲第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. A control guide tube having a control rod is connected to the lower end of the control rod, and during reactor operation, the control rod is raised and lowered inside the control rod guide tube, and the control rod is attached to and detached from the control rod by rotating at a predetermined angle with respect to the control rod. and a rotation stopper provided at the lower end of the control rod guide tube to fit the lower end of the control rod from above to prevent rotation of the control rod. Characteristic boiling water reactor. 2. The boiling water nuclear reactor according to claim 1, wherein the rotation stopper has four fitting grooves into which the lower ends of the four blades of the control rod are respectively fitted.
JP59168979A 1984-08-13 1984-08-13 Boiling water type reactor Granted JPS6147586A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59168979A JPS6147586A (en) 1984-08-13 1984-08-13 Boiling water type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59168979A JPS6147586A (en) 1984-08-13 1984-08-13 Boiling water type reactor

Publications (2)

Publication Number Publication Date
JPS6147586A JPS6147586A (en) 1986-03-08
JPH0476077B2 true JPH0476077B2 (en) 1992-12-02

Family

ID=15878103

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59168979A Granted JPS6147586A (en) 1984-08-13 1984-08-13 Boiling water type reactor

Country Status (1)

Country Link
JP (1) JPS6147586A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2507429B2 (en) * 1987-05-28 1996-06-12 株式会社東芝 Control rod handling device
US5241570A (en) * 1992-06-08 1993-08-31 General Electric Company Core-control assembly with a fixed fuel support

Also Published As

Publication number Publication date
JPS6147586A (en) 1986-03-08

Similar Documents

Publication Publication Date Title
CA1143874A (en) Control component retainer
US6934350B1 (en) Core configuration for a nuclear reactor
JPH0644064B2 (en) Extension device for thimble guide in nuclear reactor
US3267000A (en) Nuclear fuel assembly
JP2002350581A (en) Control rod joint assembly and control rod device of reactor
JPH0476077B2 (en)
US4876061A (en) Resiliently loaded lateral supports for cantilever-mounted rod guides of a pressurized water reactor
JPS61186891A (en) Upper nozzle for fuel aggregate
US4100021A (en) Nuclear reactor vessel and internals alignment apparatus
KR940004769B1 (en) Reconstitutable nuclear fuel assembly
US4110157A (en) Industrial technique
JPH0795112B2 (en) Integrated locking device for upper nozzle
JPS63140990A (en) Fuel aggregate of nuclear reactor and reassembling method thereof
JPS61226686A (en) Fuel aggregate and locking-unlocking method of upper nozzle adapter plate thereof
JPH0476076B2 (en)
US4654185A (en) Deep beam reactor vessel head and nuclear reactor including same
US5133926A (en) Extended burnup top nozzle for a nuclear fuel assembly
US5030410A (en) Vacuum system for nuclear reactor guide tube
EP0768677B1 (en) Fuel assembly structure using channel for load support and method for removing a fuel bundle from the channel
EP0773553B1 (en) Fuel assembly structure selectively using channel and coolant rod for load support and method of lifting the fuel assembly
JP2703428B2 (en) Small fast reactor
US3330734A (en) Nuclear reactor
US4709909A (en) Retention strap in a grid assembly fixture
US5592520A (en) Latch handle for a control road in a nuclear reactor
EP0266591B1 (en) Resiliently loaded lateral supports for cantilever-mounted rod guides of a pressurized water reactor