JPS6332393A - Nuclear reactor stop device - Google Patents
Nuclear reactor stop deviceInfo
- Publication number
- JPS6332393A JPS6332393A JP61175151A JP17515186A JPS6332393A JP S6332393 A JPS6332393 A JP S6332393A JP 61175151 A JP61175151 A JP 61175151A JP 17515186 A JP17515186 A JP 17515186A JP S6332393 A JPS6332393 A JP S6332393A
- Authority
- JP
- Japan
- Prior art keywords
- plug
- drive shaft
- neutron
- absorption element
- neutron absorption
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- 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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
[発明の目的]
(産業上の利用分野)
本発明はたとえばガス冷却型原子炉の後備原子炉停止装
置に適用される原子炉停止装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a nuclear reactor shutdown device applied to, for example, a back-up reactor shutdown device for a gas-cooled nuclear reactor.
(従来の技術) 第3図および第4図を参照して従来例を説明する。(Conventional technology) A conventional example will be explained with reference to FIGS. 3 and 4.
第3図はガス冷却型原子炉の!!!!略牛14成を示す
縦断面図であり、図中符号1は原子炉容器を示す。Figure 3 shows a gas-cooled nuclear reactor! ! ! ! It is a vertical cross-sectional view showing a roughly 14-dimensional structure, and the reference numeral 1 in the figure indicates a reactor vessel.
この原子炉容器1内には炉心2か設けられている。A reactor core 2 is provided within this reactor vessel 1 .
この炉心2は減速材である黒鉛ブロックを積留した中に
燃料棒3を装荷して構成されている。また、原子炉容器
1の底部にはヘリウムノjス等の冷却材を流入させる入
口管4が接続され、この入口管4内には出口管5が通っ
ている。原子炉容器1内に流入した冷却材が炉心2を上
方より下方に向かって通過し、炉心2の核反応熱で加熱
された後、出口管5から流出する。一方、原子炉容器1
の外部には熱交換器6が設けられており、出口管5から
流出した高温の冷却材がこの熱交換器6において二次冷
却材と熱交換された後、循環ポンプ7により入口管4を
介して再度原子炉容器1内に戻される。また金属材料お
よびグラファイトの高温酸化等を防止するために冷却材
を純化する純化系8が設【プられている。また前記炉心
2内には上方から制御棒案内管9か挿入されてあり、こ
の制御棒案内管9内には制御棒10が昇降自在に収容さ
れている。そして制御棒10を炉心2に対して挿入・引
(友操作することにより、炉心2の出力制御がなされて
いる。This reactor core 2 is constructed by loading fuel rods 3 into a pile of graphite blocks serving as a moderator. Further, an inlet pipe 4 is connected to the bottom of the reactor vessel 1 into which a coolant such as helium gas flows, and an outlet pipe 5 passes through the inlet pipe 4. The coolant that has flowed into the reactor vessel 1 passes through the reactor core 2 from above to below, is heated by the nuclear reaction heat of the reactor core 2, and then flows out from the outlet pipe 5. On the other hand, reactor vessel 1
A heat exchanger 6 is provided outside the outlet pipe 5, and after the high temperature coolant flowing out from the outlet pipe 5 is heat exchanged with the secondary coolant in the heat exchanger 6, the inlet pipe 4 is transferred by a circulation pump 7. The reactor is then returned to the reactor vessel 1 through the reactor vessel 1. In addition, a purification system 8 is provided to purify the coolant in order to prevent high-temperature oxidation of metal materials and graphite. Further, a control rod guide tube 9 is inserted into the reactor core 2 from above, and a control rod 10 is housed in the control rod guide tube 9 so as to be movable up and down. By inserting and pulling the control rods 10 into the reactor core 2, the output of the reactor core 2 is controlled.
なお、制御棒10の駆動は原子炉容器1の上端に設けら
れた制御棒駆動機構11によって行なわれているが、該
制御棒駆動機構11は、制御棒9にワイヤロープ12を
溶接し、このワイヤーローブ12をドラム13に巻回し
て、該トラム13をモータで駆動し、ワイヤロープ12
巻込、または繰出すことにより、制御棒1Qを昇降させ
る。The control rods 10 are driven by a control rod drive mechanism 11 provided at the upper end of the reactor vessel 1, and the control rod drive mechanism 11 consists of a wire rope 12 welded to the control rod 9 and The wire rope 12 is wound around a drum 13, and the tram 13 is driven by a motor.
The control rod 1Q is moved up and down by retracting or letting out.
一方、上記制御棒10の挿入が不可能となるような万一
の緊急事態を想定して、後備原子炉停止装置14が設け
られている。なお前記燃料棒3、制御棒10および後備
原子炉停止装置14は、いずれも複数ずつ設けられてい
るが、図では簡略1ヒしてそれぞれ1つずつ示しである
。On the other hand, in anticipation of an emergency situation in which insertion of the control rods 10 becomes impossible, a backup reactor shutdown device 14 is provided. Although a plurality of the fuel rods 3, control rods 10, and back-up reactor shutdown device 14 are provided, the figure shows one each for simplicity.
第4図tよ原子炉停止装置]4を示すもので、図中符号
15は案内管である。FIG. 4 t shows the nuclear reactor shutdown device] 4, and the reference numeral 15 in the figure is a guide tube.
この案内管15は炉心2内に上方から挿入され、その上
端は開口している。その案内管15の上方には、中性子
吸収素子貯蔵ホッパ(以下、ホッパという。)16が設
置されている。ホッパ16には、たとえば炭化■素を黒
鉛で固めた84C/C等の中性子吸収物質を10tm径
程度の球状、または径および高さとも10龍程度のペレ
ット状とした中性子吸収素子17が多数貯蔵されている
。This guide tube 15 is inserted into the reactor core 2 from above, and its upper end is open. A neutron absorption element storage hopper (hereinafter referred to as hopper) 16 is installed above the guide tube 15. The hopper 16 stores a large number of neutron absorbing elements 17 in which neutron absorbing materials, such as 84C/C made by hardening carbon carbide with graphite, are shaped into spheres with a diameter of about 10 tm or pellets with a diameter and height of about 10 tm. has been done.
前記ホッパ16の下端部は下方を小径とする円錐筒状を
なし、その下端開口を中性子吸収素子落下口18とし、
この中性子吸収素子落下口18を前記案内管15の上方
に位置させている。また中性子吸収素子落下口18は柱
状をなすプラグ19を内側より嵌合させることにより閉
塞されている。The lower end of the hopper 16 has a conical cylindrical shape with a smaller diameter at the bottom, and the lower end opening serves as a neutron absorption element drop port 18,
This neutron absorption element drop port 18 is located above the guide tube 15. Further, the neutron absorption element drop port 18 is closed by fitting a columnar plug 19 from the inside.
プラグ19は駆動軸20を介してホッパ16の上方に設
けられたプラグ駆動機構21に連結されている。The plug 19 is connected via a drive shaft 20 to a plug drive mechanism 21 provided above the hopper 16.
前記プラグ駆動機構21は、第4図に示すようにに駆動
モータ22の回動力を歯車23、歯車24を介してホー
ルねじ25に伝達し、このボールねじ25の回転をボー
ルナツト25の上下動に変換し、このボールナツト26
の上下動を接続板27を介して前記駆動@20に伝達す
る。As shown in FIG. 4, the plug drive mechanism 21 transmits the rotational force of the drive motor 22 to the hole screw 25 via gears 23 and 24, and converts the rotation of the ball screw 25 into the vertical movement of the ball nut 25. Convert this ball nut 26
The vertical movement of is transmitted to the drive@20 via the connecting plate 27.
なあ、図中符号28および29は、それぞれ接続板20
の上限位置および下限位置を検出する上限リミットスイ
ッチ、下限リミットスイッチである。また前記ホッパ1
6内には、収納筒30が設けられていおり、前記プラグ
19をこの収納筒3O内に沿って上下動させる。また前
記駆動軸20は、遮蔽体31の駆動軸貫通口31Aを貫
通してプラグ駆動機構21に接続されている。By the way, the symbols 28 and 29 in the figure are the connecting plates 20, respectively.
These are an upper limit switch and a lower limit switch that detect the upper and lower limit positions of . In addition, the hopper 1
A housing tube 30 is provided inside the housing tube 6, and the plug 19 is moved up and down along the inside of the housing tube 3O. Further, the drive shaft 20 passes through a drive shaft through hole 31A of the shield 31 and is connected to the plug drive mechanism 21.
上記構成によると、作動信号を受けると、駆動モータ2
2が正回転し、接続板27が上限リミットスイッチに当
接するまで上昇する。前記上限リミットスイッチ28の
作動により、前記駆動モータ22が停止する。接続板2
7の連動したプラグ1つが上昇して中性子吸収素子落下
口18を開放し、中性子吸収素子17が自重により案内
管15を通して炉心2内に自然落下し、原子炉を緊急停
止させる。According to the above configuration, upon receiving the actuation signal, the drive motor 2
2 rotates forward, and the connection plate 27 rises until it comes into contact with the upper limit switch. The actuation of the upper limit switch 28 causes the drive motor 22 to stop. Connection plate 2
One of the interlocking plugs 7 rises to open the neutron absorption element drop port 18, and the neutron absorption element 17 naturally falls into the reactor core 2 through the guide tube 15 due to its own weight, causing an emergency shutdown of the reactor.
(発明が解決しようとする問題点)
高温ガス冷却型原子炉は、H20,Co、H2、Co2
.02等化学的不純物と高温グラファイトおよび高温金
属との反応を最小に保つために、ヘリウムガス冷却材中
のこれらの不純物を純化系で除去する作業が行なわれる
。(Problems to be solved by the invention) High-temperature gas-cooled nuclear reactors contain H20, Co, H2, Co2
.. In order to keep the reaction of chemical impurities such as 02 with hot graphite and hot metals to a minimum, purification systems are used to remove these impurities in the helium gas coolant.
ヘリウムガス冷却材中の化学的不純物の発生源として次
の場合が考えられる。Possible sources of chemical impurities in helium gas coolant include:
■ 保守および燃料交換時における空気の混入、■ グ
ラフフィトおよび構成部材からのガス放出、
■ 蒸気発生器からの水の混入、
■ ヘリウムガス循環器の潤滑剤の混入、■ 炉心構成
部材と不純物ガスの反応、上記■から■項のうち、本発
明が解決しようとする課題は、0項の保守および燃料交
換時における空気の混入を防止することである。保守お
よび燃料交換時に空気が混入する状態はいくつか考えら
れる。後備原子炉停止装置の場合、ホッパ内には中性子
吸収素子が多数充填されており、隙間に混入した空気は
、抵抗が大きくて外部へ出にくい。■ Air contamination during maintenance and refueling, ■ Gas release from graphite and components, ■ Contamination of water from steam generators, ■ Contamination of lubricants from helium gas circulators, ■ Core components and impurity gases Among the above-mentioned items 1 to 2, the problem to be solved by the present invention is to prevent air from getting mixed in during maintenance and fuel exchange in item 0. There are several possible situations in which air may be mixed in during maintenance and fuel changes. In the case of backup reactor shutdown equipment, the hopper is filled with a large number of neutron absorption elements, and air that has entered the gap has a large resistance and is difficult to escape to the outside.
原子炉システムと一緒にガス置換する場合には、完全に
ガス置換ができない。したがってヘリウム冷却材の純化
作業に多くの時間を必要とする。When replacing gas together with a nuclear reactor system, complete gas replacement cannot be performed. Therefore, a lot of time is required to purify the helium coolant.
本発明は以上の点に基づいてなされたもので、その目的
とするところは、ホッパ単独でガス置換を行ない、ヘリ
ウムガスを封じ込めた状態で原子炉容器に組込むとによ
り原子炉容器内の空気の混入を少なくすることが可能な
原子炉停止装置を提供することにある。The present invention has been made based on the above points, and its purpose is to replace the air in the reactor vessel by replacing the gas in the hopper alone and incorporating helium gas into the reactor vessel in a sealed state. An object of the present invention is to provide a nuclear reactor shutdown device that can reduce contamination.
[発明の構成]
(問題点を解決するための手段)
以上の問題点を解決するための手段として本発明の後備
原子炉停止装置は、第1図および第2に示すごとく構成
される。[Structure of the Invention] (Means for Solving the Problems) As a means for solving the above problems, the backup nuclear reactor shutdown system of the present invention is constructed as shown in FIGS. 1 and 2.
すなわち、炉心内に上方から挿入された案内管15と、
この案内管15の上方に設置され、内部に中性子吸収素
子17を貯蔵するとともに、その下端に前記中性子吸収
素子17を前記案内管15を介して炉心内に落下させる
中性子吸収素子落下口101を備えた中性子吸収素子貯
蔵ホッパ16と、前記中性子吸収素子落下口101を閉
塞するプラグ19と、このプラグ19を上昇させ、前記
中性子吸収素子落下口101を開放するプラグ駆動機構
21と、このプラグ駆動機構21と前記プラグ19を連
結する駆動軸20と、この駆動軸20の途中に設けた圧
縮バネ102とで構成される。That is, the guide tube 15 inserted into the reactor core from above,
It is installed above the guide tube 15 to store the neutron absorbing element 17 therein, and is provided with a neutron absorbing element drop port 101 at its lower end for dropping the neutron absorbing element 17 into the reactor core through the guide tube 15. a neutron absorption element storage hopper 16, a plug 19 for closing the neutron absorption element drop port 101, a plug drive mechanism 21 for raising the plug 19 and opening the neutron absorption element drop port 101, and this plug drive mechanism. 21 and the plug 19, and a compression spring 102 provided in the middle of the drive shaft 20.
また、前記中性子吸収素子落下口101の上部か前記プ
ラグ19の外径より大きい部分101Aと、下部がプラ
グ19の外形より小ざい部分101Bで構成される。ざ
らに前記プラグ19の先端がこの中性子吸収素子落下口
101の段差部に接触して前記圧縮バネ102力で強く
押し付けられるようにし、プラグ19と中性子吸収素子
落下口101の嵌合部の隙間を塞ぎ、かつ前記駆動軸2
0の上端部の径を遮蔽体31の駆動軸貫通口31Aより
大きくして、この駆動軸20の段差部2OAを遮蔽体上
面31Bに接触させることにより駆動軸貫通口31Aと
駆動軸20の隙間を塞ぎ、かつ前記プラグ駆動機構21
は非通電時に制動力があるスプリングクローズタイプの
電磁ブレーキ104を所有し、かつ前記ホッパ16にガ
ス置換用の弁105を設置した構成を備えている。Further, the neutron absorption element drop port 101 is composed of an upper part 101A larger than the outer diameter of the plug 19, and a lower part 101B smaller than the outer diameter of the plug 19. Roughly, the tip of the plug 19 is brought into contact with the stepped part of the neutron absorption element drop port 101 and is strongly pressed by the force of the compression spring 102, thereby closing the gap between the fitting part of the plug 19 and the neutron absorption element drop port 101. and the drive shaft 2
By making the diameter of the upper end of the drive shaft 20 larger than the drive shaft through hole 31A of the shield 31 and bringing the stepped portion 2OA of the drive shaft 20 into contact with the shield upper surface 31B, the gap between the drive shaft through hole 31A and the drive shaft 20 is reduced. and the plug drive mechanism 21
It has a spring-close type electromagnetic brake 104 that provides a braking force when the power is not energized, and a valve 105 for gas replacement is installed in the hopper 16.
(作 用)
すなわら、駆動軸20の途中に圧縮バネ102を設けて
中性子吸収素子落下口101の口径の上部をプラグ19
より大きい部分101Aにし、下部をプラグ19より小
さい部分にしたことによってプラグ19より大きい部分
101Aにプラグ19を嵌め込む。これによって中性子
吸収素子17を落下させないで中性子吸収素子貯蔵ホッ
パ16内に貯蔵しておくことができ、またプラグ1つの
挿入・用法が容易に行なえる。(Function) In other words, a compression spring 102 is provided in the middle of the drive shaft 20, and the upper part of the diameter of the neutron absorption element drop port 101 is connected to the plug 19.
By making the larger portion 101A and the lower portion smaller than the plug 19, the plug 19 is fitted into the portion 101A larger than the plug 19. As a result, the neutron absorbing element 17 can be stored in the neutron absorbing element storage hopper 16 without being dropped, and one plug can be easily inserted and used.
一方、口径がプラグ19より小さい部分101Bにプラ
グ19の先端を当てて圧縮バネ102を圧縮させると圧
縮バネの102の復元力により、プラグ19の先端を強
く押し当てることができる。On the other hand, when the tip of the plug 19 is applied to a portion 101B having a smaller diameter than the plug 19 and the compression spring 102 is compressed, the restoring force of the compression spring 102 allows the tip of the plug 19 to be strongly pressed against the portion 101B.
これによって中性子吸収素子落下口からのガス漏れを防
止できる。一方、駆動軸20の上端部を遮蔽体の駆動軸
貫通口31Aより大ぎくしてこの駆動軸の段差部2OA
を遮蔽体上面31Bに押し当てる。これによって駆動軸
貫通口31Aと駆動軸20の隙間を閉塞することができ
る。また、押し当てる力は、まずプラグ駆動機溝21の
電磁ブレーキ’104に通電して制動力をなくしてポー
ルねじ25に回転トルクを加えることにより与える。This can prevent gas leakage from the neutron absorption element drop port. On the other hand, the upper end of the drive shaft 20 is made larger than the drive shaft through hole 31A of the shield, and the stepped portion 2OA of the drive shaft is
is pressed against the upper surface 31B of the shield. This allows the gap between the drive shaft through hole 31A and the drive shaft 20 to be closed. Further, the pressing force is applied by first energizing the electromagnetic brake '104 of the plug drive groove 21 to eliminate the braking force and applying rotational torque to the pole screw 25.
回動トルクを与えたところで電磁ブレーキ104の電気
を切れば、電磁ブレーキ104の制動力が動いて押し付
は力を保持できる。ホッパ16内をガス置換する時には
、第2図に示すように原子炉容器外で弁105の先に配
管と弁106、弁107を介して真空ポンプ108とヘ
リウムガス供給装置109を接続する。またガス置換時
にプラグ1つに外圧が加わり、プラグを押し上げないよ
うに中性子吸収素子落下口101の先端に真空ポンプ]
]0を接続して排気する。ホッパ内を排気した後ヘリウ
ムガスを0.1に8/cjG程度充填して弁105を締
めて弁105の先から配管、弁106.107、真空ポ
ンプ108とでヘリウムガス供給装置109および真空
ポンプ110を取外して、へりrクムガスを封じ込めた
状態で原子炉容器内に組込むことができる。If the electricity to the electromagnetic brake 104 is turned off after the rotational torque is applied, the braking force of the electromagnetic brake 104 moves and the pressing force can be maintained. When replacing the inside of the hopper 16 with gas, a vacuum pump 108 and a helium gas supply device 109 are connected outside the reactor vessel via piping and valves 106 and 107 beyond the valve 105, as shown in FIG. In addition, a vacuum pump is placed at the tip of the neutron absorption element drop port 101 to prevent external pressure from being applied to one plug during gas replacement and pushing the plug upward.]
] Connect 0 and exhaust. After evacuating the inside of the hopper, fill it with helium gas to the extent of 0.1 to 8/cjG, close the valve 105, connect the piping from the end of the valve 105, valves 106 and 107, and the vacuum pump 108 to the helium gas supply device 109 and the vacuum pump. 110 can be removed and assembled into the reactor vessel in a state where the hemicombus gas is contained.
(実施例)
以下、第1図および第2図を参照して本発明に係る原子
炉停止装置の一実施例を説明する。(Example) Hereinafter, an example of a nuclear reactor shutdown device according to the present invention will be described with reference to FIGS. 1 and 2.
なお、従来と同一部分には同一符号を付して示し、その
説明は省略する。Note that parts that are the same as those in the prior art are denoted by the same reference numerals, and their explanations will be omitted.
第1図は本実施例による原子炉停止装置の縦断面図でお
る。第2図は本発明の詳細な説明する原子炉停止装置の
縦断面図でおる。図中符号101は中性子吸収素子落下
口でおり、中性子吸収素子貯蔵ホッパ16の下端部に設
けており、通常はプラグ19によって閉塞されている。FIG. 1 is a longitudinal sectional view of a nuclear reactor shutdown device according to this embodiment. FIG. 2 is a longitudinal cross-sectional view of a nuclear reactor shutdown device explaining the present invention in detail. Reference numeral 101 in the drawing indicates a neutron absorption element drop port, which is provided at the lower end of the neutron absorption element storage hopper 16, and is normally closed by a plug 19.
この中性子吸収素子落下口101は上部がプラグ19よ
り大ぎい口径101Aと下部がプラグ19より小さい口
径101Bとで構成される。またプラグ19とプラグ駆
動機構21を連結している駆動軸20の途中に圧縮バネ
102を設けた構成である。圧縮バネ102の両端はそ
れぞれ駆動軸20に固定されており、前記プラグ19の
先端が中性子吸収素子落下口101の口径段差部に接触
して圧縮バネ102の力で押し付けられている。The neutron absorbing element drop port 101 has an upper part with a diameter 101A larger than the plug 19, and a lower part with a diameter 101B smaller than the plug 19. Further, a compression spring 102 is provided in the middle of a drive shaft 20 that connects the plug 19 and the plug drive mechanism 21. Both ends of the compression spring 102 are fixed to the drive shaft 20, and the tip of the plug 19 comes into contact with the caliber stepped portion of the neutron absorption element drop port 101 and is pressed by the force of the compression spring 102.
さらに、前記ホッパ16は遮蔽体31の下面に固定させ
ている。そして、前記駆動軸20は遮蔽体31の駆動軸
貫通口31A内を貫通してプラグ駆動優構21に接続し
ている。また駆動軸20は前記駆動軸貫通口31Aをで
たところで、前記貫通口31Aの口径より大きくなって
おり、この駆動軸段差部20AC,tl蔽体上面3’l
Bに接触している。また前記プラグ駆動機構21は非通
電時に制動力があるスプリングクローズタイプの電磁ブ
レーキ104を所有し、かつ前記ホッパ16にガス置換
用の弁105を設置した構成である。Further, the hopper 16 is fixed to the lower surface of the shield 31. The drive shaft 20 passes through the drive shaft through hole 31A of the shield 31 and is connected to the plug drive mechanism 21. Further, the drive shaft 20 has a diameter larger than that of the drive shaft through hole 31A at the point where it exits the drive shaft through hole 31A.
is in contact with B. Further, the plug drive mechanism 21 has a spring close type electromagnetic brake 104 that has a braking force when not energized, and a valve 105 for gas replacement is installed in the hopper 16.
以上の構成をもとにその作用を説明する。The operation will be explained based on the above configuration.
駆動軸20の途中に圧縮バネ102を設けて中性子吸収
素子落下口101の口径の上部をプラグ19より大きい
部分101Aにしたことでこの部分にプラグ19を嵌め
込むことかできるので中性子吸収素子17を落下させな
いでホッパ16内に貯蔵しておくことかでき、またプラ
グ19の挿入、明後きが容易に行なえる。一方、中性子
吸収素子落下口101の下部の口径をプラグ19より小
さい部分101Bにしたことでこの段差部にプラグ1つ
の先端を当てて圧縮バネ102を圧縮させると、圧縮バ
ネ1.02の復元力により、プラグ先端を強く押し当て
ることができるので、中性子吸収素子落下口からのカス
漏れを防止できる。一方、駆動軸20の上端部を遮蔽体
の駆動軸貫通口31Aより大きくしてこの駆動軸の段差
部2OAを遮蔽体上面31Bに押し当てることにより駆
動軸貫通口31Aと駆動軸20の隙間を閉塞することが
できるので駆動軸貫通口31Aからのガス漏れを防止で
きる。押し当てる力は、まずプラグ駆動機構21の電磁
ブレーキ104に通電して制動力をなくしてポールねじ
25に回転トルクを加えることにより与える。回転トル
クを加えたところで電磁ブレーキ104の電気を切れば
電磁ブレーキ104の制動力が動いて押し付は力を保持
できる。By providing a compression spring 102 in the middle of the drive shaft 20 and making the upper part of the diameter of the neutron absorption element drop port 101 a part 101A larger than the plug 19, the plug 19 can be fitted into this part. The plug 19 can be stored in the hopper 16 without being dropped, and the plug 19 can be inserted and removed easily. On the other hand, by making the diameter of the lower part of the neutron absorption element drop port 101 smaller than that of the plug 19, when the tip of one plug is applied to this stepped part and the compression spring 102 is compressed, the restoring force of the compression spring 1.02 This allows the tip of the plug to be strongly pressed against the plug, thereby preventing debris from leaking from the neutron absorption element drop port. On the other hand, by making the upper end of the drive shaft 20 larger than the drive shaft through hole 31A of the shield and pressing the stepped portion 2OA of the drive shaft against the upper surface 31B of the shield, the gap between the drive shaft through hole 31A and the drive shaft 20 is reduced. Since it can be closed, gas leakage from the drive shaft through hole 31A can be prevented. The pressing force is applied by first energizing the electromagnetic brake 104 of the plug drive mechanism 21 to eliminate the braking force, and then applying rotational torque to the pole screw 25. If the electricity to the electromagnetic brake 104 is turned off when the rotational torque is applied, the braking force of the electromagnetic brake 104 is activated and the pressing force can be maintained.
ホッパ内をガス置換する時には、第2図に示すように原
子炉容器外で弁105の先に配管と弁106、弁’10
7を介して真空ポンプ108とヘリウムガス供給装置1
09を接続する。ホッパ16内排気時にプラグ19に外
圧が加わり、プラグ19を押し上げないように中性子吸
収体落下口101の先端に真空ポンプ110を接続して
排気する。When replacing gas in the hopper, as shown in Fig. 2, outside the reactor vessel, pipes are connected to the tip of valve 105, valve 106 and valve '10.
7 via vacuum pump 108 and helium gas supply device 1
Connect 09. External pressure is applied to the plug 19 when the hopper 16 is evacuated, and a vacuum pump 110 is connected to the tip of the neutron absorber drop port 101 to prevent the plug 19 from being pushed up.
ホッパ内を排気した後ヘリウムカスを0.1kg/cm
G程度充填して弁105を閉めて弁105の先から配管
、弁106.107、真空ポンプとへりつムガス供給装
置109および真空ポンプ110を取外してヘリウムガ
スを封じ込めた状態で原子炉容器内に組込む。After exhausting the inside of the hopper, remove helium scum at a rate of 0.1 kg/cm.
G, close the valve 105, remove the piping from the end of the valve 105, the valves 106 and 107, the vacuum pump, the helium gas supply device 109, and the vacuum pump 110, and enter the reactor vessel with the helium gas sealed. Incorporate.
以上本実施例によると、中性子吸収素子落下口にプラグ
外径より大きい部分と小ざい部分を設けることと、駆動
軸に圧縮バネを追加することと、駆動軸の上部を遮蔽体
の駆動軸貫通口より大きくすることと、プラグ駆動機構
の電磁ブレーキを非通電時に制動力があるスプリングク
ローズ式の電磁弁としたことと、ホッパに弁を取付ける
こと等従来の技術に対して簡単な改造を加えることでホ
ッパ内のガス漏れを防止できる。したがって、原子炉容
器外で後備原子炉停止装置単独でガス置換を行なえるの
で、後備原子炉停止装置から原子炉容器内へ空気が混入
するのを防止でき、原子炉システムのガス置換、ガス純
化の時間が短縮できる。As described above, according to this embodiment, the neutron absorption element drop port is provided with a part larger than the outer diameter of the plug and a smaller part, a compression spring is added to the drive shaft, and the upper part of the drive shaft is passed through the drive shaft of the shield. Simple modifications were made to the conventional technology, such as making it larger than the mouth, using a spring-close type solenoid valve that provides braking force when the plug drive mechanism is not energized, and installing a valve on the hopper. This prevents gas leakage inside the hopper. Therefore, gas replacement can be performed by the backup reactor shutdown equipment alone outside the reactor vessel, which prevents air from entering the reactor vessel from the backup reactor shutdown equipment, allowing gas replacement and gas purification in the reactor system. time can be shortened.
[発明の効果]
以上詳述したように本発明による原子炉停止装置による
と、簡単な改造で、原子炉容器外で原子炉停止装置単独
でガス置換してガスの封じ込めができるので、保守およ
び燃料交換時において原子炉停止装置からの空気の混入
がなくなる。したかってヘリウムカス冷却月中の不純物
の混入が少なくなり、また原子炉システムのガス置換お
よびカス純化か容易になる。[Effects of the Invention] As detailed above, according to the reactor shutdown device according to the present invention, gas replacement and gas containment can be performed by the reactor shutdown device alone outside the reactor vessel with simple modification, making maintenance and maintenance easier. Air from the reactor shutdown equipment will not be mixed in during fuel exchange. Therefore, contamination with impurities during helium sludge cooling is reduced, and gas replacement and sludge purification of the reactor system are facilitated.
第1図および第2図は本発明の一実施例を説明するため
の図で、第1図は原子炉停止装置の縦断面図、第2図は
原子rP停止装置のガス置換時の状態を示す縦断面図、
第3図および第4図は従来例を説明するための図で、第
3図はガス冷却型原子炉の概略構成を示す縦断面図、第
4図は原子炉停止装置の縦断面図である。
1・・・・・・・・・原子炉容器
2・・・・・・・・・炉 心
16・・・・・・・・・ホッパ
17・・・・・・・・・中性子吸収素子19・・・・・
・・・・プラグ
20・・・・・・・・・駆動軸
2OA・・・・・・駆動軸段差部
101・・・・・・・・・中性子吸収素子落下口101
A・・・・・・プラグ外径より大きい口径部101B・
・・・・・プラグ外径より小さい口径部102・・・・
・・・・・圧縮バネ
104・・・・・・・・・非通電時に制動力のある電磁
ブレーキ
出願人 株式会社 東芝
代理人 弁理士 須 山 佐 −
第1図
第2図
第3図Figures 1 and 2 are diagrams for explaining one embodiment of the present invention. Figure 1 is a vertical cross-sectional view of the nuclear reactor shutdown equipment, and Figure 2 shows the state of the atomic rP shutdown equipment during gas replacement. A longitudinal cross-sectional view showing,
Figures 3 and 4 are diagrams for explaining conventional examples, where Figure 3 is a vertical cross-sectional view showing a schematic configuration of a gas-cooled nuclear reactor, and Figure 4 is a vertical cross-sectional view of a reactor shutdown device. . 1... Reactor vessel 2... Reactor core 16... Hopper 17... Neutron absorption element 19・・・・・・
...Plug 20... Drive shaft 2OA... Drive shaft step portion 101... Neutron absorption element drop port 101
A: Bore portion 101B larger than the outer diameter of the plug.
...Bore diameter portion 102 smaller than the outer diameter of the plug...
... Compression spring 104 ...... Electromagnetic brake with braking force when not energized Applicant Toshiba Corporation Representative Patent attorney Sa Suyama - Figure 1 Figure 2 Figure 3
Claims (1)
管の上方に設置され、内部に中性子吸収素子を貯蔵する
とともに、その下端に前記中性子吸収素子を前記案内管
を介して炉心内に落下させる中性子吸収素子落下口を備
えた中性子吸収素子貯蔵ホッパと、前記中性子吸収素子
落下口を閉塞するプラグ、そのプラグを上昇させ、前記
中性子吸収素子落下口を開放する駆動機構と、この駆動
機構と前記プラグを連結する駆動軸と、駆動軸途中に設
けた圧縮バネと、前記中性子吸収素子落下口の上部の口
径を前記プラグ外径より大きくし、中性子吸収素子落下
口の下部の口径を前記プラグより小さくし、プラグの先
端がこの中性子吸収素子落下口段差部に接触して前記圧
縮バネの力で強く押し付けられるようにし、かつ前記駆
動軸の上端部を遮蔽体の駆動軸貫通口より大きくして、
この段差部を遮蔽体上面に接触させ、かつ前記駆動非通
電時に制動力を有するスプリングクローズタイプの電磁
ブレーキを備え、かつ前記ホッパにガス置換用の弁を設
置したことを特徴とする原子炉停止装置。(1) A guide tube inserted into the reactor core from above, installed above the guide tube, stores a neutron absorption element inside, and inserts the neutron absorption element into the core through the guide tube at its lower end. a neutron absorbing element storage hopper equipped with a neutron absorbing element dropping port for dropping the neutron absorbing element into the neutron absorbing element; a plug for closing the neutron absorbing element dropping port; a drive mechanism for raising the plug and opening the neutron absorbing element dropping port; A drive shaft connecting the mechanism and the plug, a compression spring provided in the middle of the drive shaft, and a diameter of the upper part of the neutron absorption element drop port are made larger than the outer diameter of the plug, and a diameter of the lower part of the neutron absorption element drop port is made larger than the outer diameter of the plug. The tip of the plug is made smaller than the plug so that the tip of the plug comes into contact with the stepped portion of the neutron absorption element drop port and is strongly pressed by the force of the compression spring, and the upper end of the drive shaft is made smaller than the drive shaft through hole of the shield. Make it bigger
The nuclear reactor shutdown is characterized in that the stepped portion is brought into contact with the upper surface of the shield, a spring close type electromagnetic brake is provided which has a braking force when the drive is not energized, and a valve for gas replacement is installed in the hopper. Device.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61175151A JPS6332393A (en) | 1986-07-25 | 1986-07-25 | Nuclear reactor stop device |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61175151A JPS6332393A (en) | 1986-07-25 | 1986-07-25 | Nuclear reactor stop device |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6332393A true JPS6332393A (en) | 1988-02-12 |
Family
ID=15991162
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP61175151A Pending JPS6332393A (en) | 1986-07-25 | 1986-07-25 | Nuclear reactor stop device |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6332393A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US7067731B2 (en) | 1999-11-29 | 2006-06-27 | Yamaha Corporation | Sound source circuit and telephone terminal using same |
-
1986
- 1986-07-25 JP JP61175151A patent/JPS6332393A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US7067731B2 (en) | 1999-11-29 | 2006-06-27 | Yamaha Corporation | Sound source circuit and telephone terminal using same |
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