JPS613084A - Boiling-water type reactor - Google Patents

Boiling-water type reactor

Info

Publication number
JPS613084A
JPS613084A JP59124688A JP12468884A JPS613084A JP S613084 A JPS613084 A JP S613084A JP 59124688 A JP59124688 A JP 59124688A JP 12468884 A JP12468884 A JP 12468884A JP S613084 A JPS613084 A JP S613084A
Authority
JP
Japan
Prior art keywords
control rod
guide tube
crd
reactor
core
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
JP59124688A
Other languages
Japanese (ja)
Other versions
JPH0476076B2 (en
Inventor
今崎 善夫
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to 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

  • Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

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】 [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 control rods 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の内部に炉心シュラウド2が設けら
れ、この炉心シュラウド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は角筒状のチャンネルボック
ス内に多数の燃料棒を収容してなるもので、平面図上に
おいては炉心シュラウド2内にマトリックス状になるよ
うに配列されており、原子炉圧力容器1内の底部より上
方へ向っ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枚のフィンガ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枚のフィ
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っている。
[Technical Background of the Invention] As shown in FIG. 5, in a BWR, a core shroud 2 is provided inside a reactor pressure vessel 1 that accommodates a coolant (soft water), and a reactor core provided in this core shroud 2 is used. Support plate 3
A reactor core 5 is constructed by loading a large number of fuel assemblies 4 thereon. Each of the fuel assemblies 4 has 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. 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. The fuel assemblies 4 are interposed between the fuel assemblies 4 and are arranged at a ratio of one for every four fuel assemblies 4. By inserting each CR6 from below between the fuel assemblies 4, the core output is suppressed according to the insertion amount, and by pulling out each CR6 downward from between the fuel assemblies 4, the core output is increased. The configuration is such that output control is performed during reactor operation.

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
曙橋(以下CRDと称する)8が設けられている。
In addition, 7 in FIG. 5 is a cylindrical control rod guide tube (hereinafter referred to as a CR guide tube) provided below the core 5 corresponding to each CR6, and this CR guide tube 7 is shown in FIG. As shown, each CR6 is inserted into the interior to guide the CR6 as it moves up and down during normal operation of the reactor. A control rod drive bridge (hereinafter referred to as CRD) 8 is provided below the reactor pressure vessel 1 to drive the CR 6 up and down.

前記炉心シュラウド2の上端はシュラウドヘッド9で閉
塞されており、このシュラウドヘッド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 by a shroud head 9, and a steam separator 10 is connected above the shroud head 9. 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
ビン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。
The CR guide tube 7 is connected to the core support plate 3 as shown in FIG.
It penetrates through and its upper end outer peripheral part is supported by the core support plate 3,
Furthermore, its upper end is engaged with a pin 12 protruding from the upper surface of the core support plate 3, thereby inhibiting its rotation. 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1
6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、C
RD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.
6 and a motor section 17 for driving the motor section 6 up and down.
With CRD exposed below the CRD housing 15,
It is attached to the lower end flange portion 15a of the RD 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−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1
8aよりなるバヨネット式連結部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が上方向へ向って突設され、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18a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
ネット式被連結部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1
9aの底面が支持棒18cに当接し、CR6の重量が支
持棒18cによっ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 thereof are shown in FIGS. 9(a) and (b) and FIGS. 10(a) and (b). That is, at the upper end of the piston 16 of the CRD 8, four vertically long engagement pieces 1 are arranged at equal intervals in the circumferential direction.
A bayonet type connecting portion 18 consisting of 8a is provided, and a bulging portion 18b is formed at the tip of the outer surface of each engaging piece 18a. Furthermore, a support rod 18c is provided at the center of the four engaging pieces 18a to protrude upward, and this support rod 18c
This limits the amount of inward deflection of the four engaging pieces 18a. On the other hand, the connecting portion 18 is located at the lower end of CR6.
A recess 19a for accommodating the bayonet is provided, and four engaging protrusions 19b are protruded at equal intervals in the circumferential direction from the open end of the inner circumferential surface of the recess 19a so as to correspond to the respective engaging pieces 18a. A type connected portion 19 is configured. When the connecting portion 18 and the connected portion 19 are connected, the recess 1
The bottom surface of CR 9a comes into contact with support rod 18c, and the weight of CR6 comes to be supported by 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、CR6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C
RD8側の係合片18aが第9図(a)、(b)の如く
係合突起19b tillを通過するようにし、支持棒
18cが凹所19a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内の保合突
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OR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CRD
8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を凹所19a内の保合突起
19bより外し、係合片18aが係合突起19b間を通
過するようにして係合ピストン16を下降させていく。
Therefore, the attachment and detachment of the CR6 and the CRD 8 is performed with the CR6 lowered further than the operating range during nuclear reactor operation, and with the lower end of the CR6 seated on the seat surface 14 of the CR guide tube 7. That is, the connection between CR6 and CRD8 is
First, seat the CR6 on the seat surface 14 of the CR guide tube 7,
The piston 16 of CRD8 is raised. At this time C
The engaging piece 18a on the RD8 side passes through the engaging protrusion 19b till as shown in FIGS.
10(a) and 10(b), the bulging portion 18b of each engaging piece 18a is engaged with the retaining protrusion 19b in the recess 19a. To disconnect the CR6 and CRD8, first connect the CR6 to the seat surface 14 of the OR guide tube 7.
from the state shown in Figures 10(a) and (b).
8 by approximately 45 degrees to remove the bulging portion 18b of each engaging piece 18a from the retaining protrusion 19b in the recess 19a as shown in FIGS. 9(a) and 9(b), and the engaging piece 18a is engaged. The engagement piston 16 is lowered so as to pass between the protrusions 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OR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
、ORのフィ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、各フィンガは薄く、しかも長さが長い
(約4m)ため、CRDとの@説の際に下端部に回転力
る作業性および健全性に問題があった。
[Problems with Background Art] In a BWR in which the CR and CRD can be attached and detached by mutually rotating them by a predetermined angle, when the CR is lowered to a position where it is seated on the seat surface of the OR guide tube, Since the upper ends of the OR fingers are interposed between adjacent fuel assemblies, rotation is prohibited by these fuel assemblies, but each finger is thin and long (approximately 4 m), so the CRD When using the @ theory, there was a problem with workability and soundness due to rotational force at the lower end.

[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ORの下端部に回転力が作用
しても、ORにねじれが生じることのないようにし、I
IH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
The purpose of this is to enable the CR and CRD to be attached and detached by rotating them by a predetermined angle.
Even if rotational force is applied to the lower end of the OR when attaching and detaching the CRD and the I
The objective is to improve workability and CR soundness during IH.

[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・明
後動作して原子炉運転時の出力制卸を行なう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
ORに対する案内機能を有するとともに下端部にORを
着座させるシート面を有するOR案内管と、前記ORの
下端に連結して原子炉運転時にはそのCRをOR案内管
の内部で昇降させ、CRの1脱はORを前記OR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
することによって行なうCRDと、前記CRの下端部と
前記OR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C
R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 object, the present invention provides a CR that is inserted into the reactor core and operates after the morning to control the output during reactor operation, and a CR that is inserted into the reactor core to control the output during reactor operation. an OR guide tube that has a guiding function for the OR that moves up and down during reactor operation and has a seat surface at its lower end for seating the OR; and an OR guide tube that is connected to the lower end of the OR and that allows the CR to move up and down inside the OR guide tube during reactor operation. , one removal of the CR is performed by rotating the OR at a predetermined angle relative to the CR with the OR seated on the seat surface of the OR guide tube. It is provided so that it can be fitted in a concave and convex manner from the top and bottom directions, and the C when the CR and CRD are attached and detached.
It is configured to include an engaging part and an engaged part that prohibit rotation of R.

[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の内部には′炉
心シュラウド102が設けられ、この炉心シュラウド1
02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は角筒状のチャンネルボックス内
に多数の燃料棒を収容してなるもので、平面図上におい
て炉心シュラウド102内にマトリックス状になるよう
に配列されており、原子炉圧力容器101内の底部より
上方へ向って流通する冷却材を核反応熱で加熱する。
[Embodiment of the invention] Figures 1 to 4 show an embodiment of the present invention,
FIG. 1 shows a schematic configuration of a BWR. That is, the coolant (
A core shroud 102 is provided inside the reactor pressure vessel 101 that accommodates soft water).
A core 105 is constructed by loading a large number of fuel assemblies 104 onto a core support plate 103 provided within the core 102. Each of the fuel assemblies 104 is made up of a large number of fuel rods housed in a rectangular cylindrical channel box, and is arranged in a matrix shape in the core shroud 102 in a plan view, and the reactor pressure The coolant flowing upward from the bottom of the container 101 is heated by nuclear reaction heat.

また炉心105にはOR10Bが配設されている。この
CR10Gは中性子吸収物質を内蔵した4枚のフィンガ
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枚のフィ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104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
われる構成となっている。
Further, an OR 10B is arranged in the reactor core 105. This CR10G is constructed by combining four fingers containing a neutron absorbing material so that the cross section becomes cross-shaped, and each of the four fingers is interposed between adjacent fuel assemblies 104. One fuel assembly per fuel assembly 104 is arranged. By inserting each CR106 from below between the fuel assemblies 104, the core output is suppressed according to the insertion amount, and by pulling out each CR106 downward from 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CRIO6
ごとに対応して設けられた円筒形状のOR案内管で、こ
のOR案内管107は各C,R106を内部に挿通させ
、原子炉通常運転時に昇降動作する0R106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CHD108が設けられて
いる。
In addition, 107 in the figure indicates each CRIO 6 below the core 105.
This OR guide tube 107 is a cylindrical OR guide tube provided correspondingly to each C and R106, and is used to guide the OR106 that moves up and down during normal operation of the reactor. A CHD 108 is provided below the reactor pressure vessel 101 to drive the CR 106 up and down.

前記炉心シュラウド102の上端はシュラウドヘッド1
09で閉塞されており、このシュラウドヘツドラ09上
には気水分離器110が接続されている。
The upper end of the core shroud 102 is the shroud head 1
09, and a steam/water separator 110 is connected above this shroud header 09.

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
1110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11
1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。
This steam/water separator 110 separates the coolant vapor heated and evaporated in the core 105 into steam and water, and furthermore, a steam dryer 111 is connected above the steam/water 1110 to dry the separated steam. has been done. and steam dryer 11
The steam that has passed through the reactor vessel 101 is sent to a generator-driving turbine outside the reactor vessel 101 through a main steam pipe (not shown).

前記OR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ビ
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@ 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OR案内管101の内周面下端部には第2図
に示す如< 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、OR案内管101の下
端部には係止部113が設けられている。
The OR guide tube 107 passes through the core support plate 103 and has its upper end outer periphery suspended on the core support plate 103, and further has its upper end engaged with a bottle protruding from the upper surface side of the core support plate 103. Its rotation is prohibited. Also, each CR
Fuel supports that support the fuel assembly 104 from below are formed at the four corners of the upper end of the guide @ 107, respectively. Furthermore, a seat surface 112 is provided at the lower end of the inner circumferential surface of the OR guide tube 101, as shown in FIG. 2, on which the lower end of the CR 106 is seated. Furthermore, a locking portion 113 is provided at the lower end of the OR guide tube 101.

前記CRD 108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OR
案内管107の係止部113を上方より導入させている
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. In this CRD housing 114, the OR
The locking portion 113 of the guide tube 107 is introduced from above.

CRD 108は前記CRDハウジング114の内周に
嵌合するアウターチューブ115の上端に被係止部11
6を有し、この被係止部116と前記OR案内管101
の係止部113とで互いに係脱自在なバヨネット連結機
構が構成されている。そしてざらにCRD 1Hは上記
アウターチューブ115内を昇降動作するピストン11
7、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114aにボルト等により取
付けられている。
The CRD 108 has a locked portion 11 at the upper end of an outer tube 115 that fits into the inner periphery of the CRD housing 114.
6, and this locked portion 116 and the OR guide tube 101
The locking portion 113 constitutes a bayonet connection mechanism that can be freely engaged and detached from each other. Roughly CRD 1H is a piston 11 that moves up and down inside the outer tube 115.
7. Motor section 118 that drives the piston 117 up and down
(See FIG. 1), and is attached to the lower end flange portion 114a of the CRD housing 114 with bolts or the like, with the motor portion 118 exposed below the CRD housing 114.

前記CR0108のピストン117上端には、周方向等
間隔に配置された4本のたて艮な係合片119aよりな
るバヨネット式連結部119が設けられ、各保合片11
9a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本の保合片119aの中央には支持棒
119Cが上方向へ向って突設され、この支持棒119
Cで4本の保合片119aの内方へのたわみ量を制限す
るようにしている。一方、CR10B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つの保合突起120bを周方向等間
隔に突出させてバヨネット式被連結部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119
Cに当接し、CR106の重量が支持棒119Cによっ
て支持されるようになる。
The upper end of the piston 117 of the CR0108 is provided with a bayonet type connecting portion 119 consisting of four vertical engagement pieces 119a arranged at equal intervals in the circumferential direction, and each engagement piece 11
A bulge 119b is formed at the tip of the outer surface of 9a. Furthermore, a support rod 119C is provided in the center of the four retaining pieces 119a to protrude upward, and this support rod 119
C limits the amount of inward deflection of the four retaining pieces 119a. On the other hand, a recess 120a for accommodating the connecting portion 119 is provided at the lower end of the CR10B, and each of the engaging pieces 119a is provided at the open end of the inner peripheral surface of the recess 120a.
The bayonet type connected portion 120 is configured by projecting four locking protrusions 120b at equal intervals in the circumferential direction so as to correspond to the above. When the connecting portion 119 and the connected portion 120 are connected, the bottom surface of the recess 120a is connected to the support rod 119.
C, and the weight of the CR 106 comes to be supported by the support rod 119C.

前記Q R106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OR案内管107の下部には、CR1
06の上記係合部121が設けられている箇所を囲む位
置に円筒部122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< CR106をOR案内管107のシート面11
2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。
At the outer periphery of the lower end of the Q R106, there are
As shown in the figure, an engaging portion 121 formed of one or more convex portions (the figure shows an example in which two convex portions are provided) is provided in a protruding manner. On the other hand, at the bottom of the OR guide tube 107, CR1
A cylindrical portion 122 is provided at a position surrounding the portion where the above-mentioned engaging portion 121 of 06 is provided, and the inner peripheral surface of this cylindrical portion 122 has convex portions corresponding to each convex portion of the above-mentioned engaging portion 121. Engaged portions 123 made up of the same number of recesses are provided. As shown in FIG. 2, these engaging portions 121 and engaged portions 123
When lowered to the position where the seat 2 is seated, they fit into each other from above and below.

そこでCR106とCRD 108との着脱は、CR1
06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。
Therefore, to attach and detach CR106 and CRD 108, use CR1
06 is further lowered than the operating range during reactor operation, and the lower end of the CR 106 is seated on the seat surface 112 of the CRD guide tube 107.

すなわち、CR106とCRD 108との連結は、ま
ずCR1013をOR案内管107のシート面112に
着座させ、CHD 108のピストン117を上昇させ
ていく。このときCRD 108側の係合片119aが
係合突起120b問を通過するようにし、支持棒119
Cが凹所120aの底面に当接したところでCRD 1
0B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、CRioaとCRD 108との連結解
除は、まずCR106をOR案内管107のシート面1
12に着座させ、CRD 108を約45°回転させて
各係合片119aノ膨出8I1119b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11
7を下降させていく。
That is, to connect the CR 106 and the CRD 108, first the CR 1013 is seated on the seat surface 112 of the OR guide tube 107, and the piston 117 of the CHD 108 is raised. At this time, the engagement piece 119a on the CRD 108 side is made to pass through the engagement protrusion 120b, and the support rod 119
When C contacts the bottom of the recess 120a, CRD 1
0B is rotated about 45 degrees to engage the bulging portion 119b of each engagement piece 119a with the engagement protrusion 120b in the recess 120a. Also, to disconnect CRioa and CRD 108, first connect CR106 to seat surface 1 of OR guide tube 107.
12, and rotate the CRD 108 by about 45 degrees so that the bulge 8I1119b of each engagement piece 119a is aligned with the recess 120a.
The engagement piston 11 is removed from the inner engagement protrusion 120b, and the engagement piece 119a passes between the engagement protrusions 120b.
7 will be lowered.

そしてこのようにしてCR100とCRD 108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、CR0108をCR106に対して回転させた場合
でもCR106の下端部がCRD 108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
がって、CR106とCRD 108との着脱時におけ
る作業性が改善され、CR,106の健全性も向上する
ことになる。
When attaching and detaching the CR100 and the CRD 108 in this manner, the lower end of the CR106 is prohibited from rotating due to the engagement between the engaging portion 121 and the engaged portion 123, so the CR0108 is not connected to the CR106. Even when rotated, the lower end of the CR 106 does not rotate following the CRD 108, and no twisting or the like occurs. Therefore, the workability when attaching and detaching the CR 106 and 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121を凸
部とし、CR0108側の被係合部123を凹部とした
が、凸部と凹部とを逆の関係にしてもよい。
In the above embodiment, the engaging portion 121 on the CR106 side is a convex portion, and the engaged portion 123 on the CR0108 side is a concave portion, but the relationship between the convex portion and the concave portion may be reversed.

談だ、それら凸部および凹部の数も任意に設定可能であ
る。
Furthermore, 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OR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11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 described in detail above, according to the BWR of the present invention, the lower end of the CR and the upper end of the OR guide tube are provided so as to be able to engage with each other in a recessed and recessed manner from the vertical direction, and the CR and CRD are By providing an engaging portion and an engaged portion that prohibit rotation of the CR during attachment/detachment, even if a rotational force is applied to the lower end of the CR when detaching the CR and the CRD, the CR will not be twisted. There is no occurrence of this problem, and the workability during attachment and detachment and the soundness of the CR can be improved.

【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OR
案内管とCRDとの接続部周辺の断面図、第3図は第2
図の11断面図、第4図はCRの係合部とOR案内管の
被保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Vl−VT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IN−IX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X−X断面図である。 105・・・炉心、106・・・CR(制御棒) 、1
07・・・OR案内管(制御棒) 、108・・・CR
D (制御棒駆動機構) 、112・・・シート面、1
21・・・係合部、123・・・被係合部。 出願人代理人 弁理士 鈴江武彦 第2図 第  3 図 第 4 図 第6図 第7図 第8図
1 to 4 show an embodiment of the present invention,
Figure 1 is a sectional view showing the schematic configuration of BWR, Figure 2 is OR
A cross-sectional view of the area around the connection between the guide tube and CRD, Figure 3 is
11 in the figure, FIG. 4 is a perspective view showing the relationship between the engaging part of the CR and the secured part of the OR guide tube, and FIGS. 5 to 10 are for explaining the background art. The figure is a sectional view showing the schematic configuration of BWR, FIG. 6 is a Vl-VT sectional view of FIG. 8,
Fig. 7 is a sectional view taken along the line ■-■ in Fig. 8, Fig. 9 (a) is a sectional view showing a disconnected state of CR and CRD, and Fig. 9 (b) is an IN-IX cross section in Fig. 8 (a). Figure 10(a) is a sectional view showing the connection state of CR and CRD, and Figure 10(b) is the same figure (
It is a XX sectional view of a). 105...Reactor core, 106...CR (control rod), 1
07...OR guide tube (control rod), 108...CR
D (control rod drive mechanism), 112... seat surface, 1
21... Engaging portion, 123... Engaged portion. Applicant's Representative Patent Attorney Takehiko Suzue Figure 2 Figure 3 Figure 4 Figure 6 Figure 7 Figure 8

Claims (2)

【特許請求の範囲】[Claims] (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
回転することによっ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。
(1) A control rod that is inserted into and pulled out of the reactor core to control output during reactor operation, and a control rod that is inserted inside and has a guiding function for the control rod that moves up and down during reactor operation, and the lower end A control rod guide tube having a seat surface on which a control rod is seated; 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, and attachment and detachment to the control rod is controlled. a control rod drive mechanism that rotates the rod at a predetermined angle relative to the control rod while seated on the seat surface of the control rod guide tube; and a lower end of the control rod and a lower end of the control rod guide tube. Boiling water characterized by comprising 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 and detached. type reactor.
(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。
(2) 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. boiling 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 true JPS613084A (en) 1986-01-09
JPH0476076B2 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)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014521944A (en) * 2011-07-29 2014-08-28 アレヴァ ゲゼルシャフト ミット ベシュレンクテル ハフツング Connection between reactor control rod guide tube and drive housing tube

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014521944A (en) * 2011-07-29 2014-08-28 アレヴァ ゲゼルシャフト ミット ベシュレンクテル ハフツング Connection between reactor control rod guide tube and drive housing tube

Also Published As

Publication number Publication date
JPH0476076B2 (en) 1992-12-02

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