JPS60147687A - Nuclear reactor - Google Patents

Nuclear reactor

Info

Publication number
JPS60147687A
JPS60147687A JP59004508A JP450884A JPS60147687A JP S60147687 A JPS60147687 A JP S60147687A JP 59004508 A JP59004508 A JP 59004508A JP 450884 A JP450884 A JP 450884A JP S60147687 A JPS60147687 A JP S60147687A
Authority
JP
Japan
Prior art keywords
control rod
reactor
pressure vessel
storage box
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.)
Pending
Application number
JP59004508A
Other languages
Japanese (ja)
Inventor
香川 達雄
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
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group 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 Toshiba Corp, Nippon Genshiryoku Jigyo KK, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP59004508A priority Critical patent/JPS60147687A/en
Publication of JPS60147687A publication Critical patent/JPS60147687A/en
Pending 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

  • Treatment Of Water By Oxidation Or Reduction (AREA)
  • Analysing Materials By The Use Of Radiation (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〕 本発明は原子炉に係シ、特に制御棒およびその駆動機構
の改良に関する〇 〔発明の技術的背景とその問題点〕 従来、原子炉の制御棒駆動機構は、制御棒に連続する支
持部の上部または下部に設置され、また駆動用モータは
、原子炉圧力容器の外部に設置されていた。このため、
原子炉圧力容器内に占める制御棒支持部および駆動機構
部が極めて長大となυ、また原子炉外にある駆動機構部
モータ部も長くなシ、原子炉圧力容器の小型化および原
子炉全体の高さの低減化が不可能であった。特に原子炉
圧力容器内に熱交換器を設置するタイプの原子炉におい
ては、原子炉炉心上部空間の利用に大きな障害があった
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to nuclear reactors, and in particular to improvements in control rods and their drive mechanisms. The rod drive mechanism was installed at the top or bottom of the support section continuous with the control rods, and the drive motor was installed outside the reactor pressure vessel. For this reason,
The control rod support section and drive mechanism section occupying inside the reactor pressure vessel are extremely long, and the drive mechanism motor section outside the reactor is also long, making it possible to downsize the reactor pressure vessel and reduce the overall size of the reactor. It was impossible to reduce the height. Particularly in a type of nuclear reactor in which a heat exchanger is installed within the reactor pressure vessel, there has been a major problem in utilizing the space above the reactor core.

〔発明の目的〕[Purpose of the invention]

本発明はかかる現況に鑑みなされたもので、制御棒駆動
機構の原子炉圧力容器内に占める体積を可及的小さくす
ることができるとともに、構造および取扱いの簡略化を
図ることができ、また原子炉全体を小型化し全体の高さ
を低くして耐震性を向上させることができ、かつ建屋を
小型化して建設および保守コストを低減させることがで
きる原子炉を提供することを目的とする。
The present invention was made in view of the current situation, and it is possible to reduce the volume occupied by the control rod drive mechanism in the reactor pressure vessel as much as possible, simplify the structure and handling, and make it possible to It is an object of the present invention to provide a nuclear reactor whose entire reactor can be downsized and its height can be reduced to improve earthquake resistance, and whose building can be downsized to reduce construction and maintenance costs.

〔発明の概装〕[Outline of the invention]

本発明は前記目的を達成する手段として、炉心内に複数
個配置された水密構造の制御棒案内管と、この制御棒案
内管の少なくとも上下いずれか一端部に連結された水蜜
構造の収容箱と、この収容箱内に屈曲状態で収容され駆
動装置により前記制御棒案内管内に繰出される制御棒と
から原子炉を構成するようにしたことを特徴とする。
The present invention provides, as means for achieving the above object, a plurality of control rod guide tubes with a watertight structure arranged in a reactor core, and a storage box with a watertight structure connected to at least one of the upper and lower ends of the control rod guide tubes. A nuclear reactor is constructed of a control rod that is accommodated in the housing box in a bent state and is fed out into the control rod guide tube by a drive device.

〔発明の実施例〕[Embodiments of the invention]

以下本発明の一実施例を図面を参照して説明する。 An embodiment of the present invention will be described below with reference to the drawings.

第7図は熱交換器を原子炉圧力容器内に設置した自然循
環冷却方式の原子炉を示すもので、図においてlは原子
炉圧力容器であシ、この原子炉圧力容器/内には、その
中央部下方に炉心λが・またその上部に冷却材の浮力を
拡大するライザ3が・さらにその上方に熱交換器ψがそ
れぞれ設置されている。
Figure 7 shows a natural circulation cooling type reactor in which a heat exchanger is installed inside the reactor pressure vessel. In the figure, l is the reactor pressure vessel, and inside this reactor pressure vessel, A reactor core λ is installed below the center, a riser 3 for increasing the buoyancy of the coolant is installed above it, and a heat exchanger ψ is installed above it.

前記炉心コの下端部には、第1図に示すように炉心下部
/ IJフッドが設置されておシ、また炉心λ内には、
炉心内燃料チャネルに平行に平板状の水密構造をなす複
数の制御棒案内管6が下方から挿入配置され、各制御棒
案内管6は、前記炉心下部グリッドjにそれぞれ固定さ
れている。
At the lower end of the core, a lower core/IJ hood is installed as shown in Figure 1, and inside the core,
A plurality of control rod guide tubes 6 having a flat plate-like watertight structure are inserted from below parallel to the in-core fuel channel, and each control rod guide tube 6 is fixed to the core lower grid j, respectively.

これら各制御棒案内管内の下端部には、第1図および第
2図に示すように水蜜構造の収容箱7がそれぞれ連結さ
れ、これら各収容箱7は、第2図に示すように炉心下部
グリッド取付部ざに固定されている。
As shown in FIGS. 1 and 2, storage boxes 7 each having a honeycomb structure are connected to the lower ends of each of these control rod guide tubes. It is fixed to the grid mounting part.

またこの収容箱7内には、第1図に示すように減速機お
よびブレーキ(いずれも図示せず)を内蔵する駆動用モ
ータタ、後に詳述する駆動機構部、および屈曲状態で収
容可能な制御棒10がそれぞれ配置され、また収容箱7
内は、大気圧または一定圧の気体で満たされていて前記
駆動機構部の潤滑や腐蝕に対してメンテナンスフリーと
なっている。
As shown in FIG. 1, this storage box 7 also contains a drive motor that incorporates a reducer and a brake (none of which are shown), a drive mechanism section that will be described in detail later, and a control unit that can be accommodated in a bent state. The rods 10 are arranged respectively, and the storage box 7
The interior is filled with gas at atmospheric pressure or a constant pressure, making maintenance free for lubrication and corrosion of the drive mechanism.

また各収容箱7内に収納された前記駆動モータタ用の電
力および信号の送電線//は、第1図に示すように高圧
水から防護する可撓性を有する電線管12内を通して前
記原子炉圧力容器l外に引出されている。そして前記′
fJLal管lコの収容箱7との接続部および原子炉圧
力容器/の貫通部は、第1図に示すように水密シール1
3によシそれぞれ水蜜構造となっている。
Further, as shown in FIG. 1, the power and signal transmission lines for the drive motors housed in each storage box 7 are passed through a flexible electric conduit 12 that protects the reactor from high-pressure water. It has been pulled out of the pressure vessel. and said′
The connection part of the fJLal pipe with the storage box 7 and the penetration part of the reactor pressure vessel are sealed with a watertight seal 1 as shown in FIG.
Each of the three types has a water honey structure.

前記駆動機構部は、第2図に示すように収容箱7の中央
部に設置した駆動用モータタの上下部にそれぞれ配され
た駆動ギヤ/4’を備えておシ、これら両駆動ギヤ/4
’は、駆動用モータタの出力軸に固設したベベルギヤ/
Sおよび駆動ギヤ/4’と一体のベベルギヤ/Aを介し
て駆動用モータタと連結され、ターミナル/7を介して
駆動モータタに送られてくる制御信号により可変速で正
逆回転駆動されるようになっている0そして前記制御棒
10は、これら両駆動ギヤ/4’に掛は渡されて/回転
中巻取った状態で収容箱7内に屈曲収容されておシ、駆
動ギヤ/4’の正転によシ前記制御棒案内晋6側に繰出
されるとともに、駆動ギヤ/ダの逆転により収容箱7内
に収容されるようになっている0 この収容箱7内にはまた、第2図に示すようにガイドギ
ヤ/gおよび案内用仕切板/9がそれぞれ設置され、制
御棒10の姿勢を常時正規状態に維持するようになって
いる。
As shown in FIG. 2, the drive mechanism section includes drive gears /4' disposed at the top and bottom of a drive motor installed in the center of the storage box 7, and these drive gears /4'.
' is a bevel gear fixed to the output shaft of the drive motor.
It is connected to the drive motor via a bevel gear /A that is integrated with S and drive gear /4', and is driven to rotate in forward and reverse directions at a variable speed by a control signal sent to the drive motor through terminal /7. 0, and the control rod 10 is hooked to both drive gears /4' and is bent and accommodated in the storage box 7 in a wound state during rotation. When the control rod is rotated in the normal direction, it is fed out to the side of the control rod guide 6, and when the drive gear is reversed, it is accommodated in the storage box 7. As shown in the figure, a guide gear /g and a guide partition plate /9 are installed to maintain the attitude of the control rod 10 in a normal state at all times.

一方前記制御棒10は、例えは第3図および第4図に示
すように金属シースに納められた多数のポイズン板20
と、これらの両側位置を屈曲自在に連結する2本のチェ
ーン2/と、各チェーン2/の外側に多数配置され制御
棒IO作動時の抵抗を軽減させるためのガイドローラ、
22とを備えておシ、前記駆動ギヤ/りおよびガイドギ
ヤ/gは、前記両チェーン2/に噛合するようになって
いる。
On the other hand, the control rod 10 includes a number of poison plates 20 housed in a metal sheath, as shown in FIGS. 3 and 4, for example.
, two chains 2/ that bendably connect these positions on both sides, and a large number of guide rollers arranged on the outside of each chain 2/ to reduce resistance when the control rod IO is operated.
22, the drive gear and the guide gear are adapted to mesh with both chains.

次に作用について説明する。Next, the effect will be explained.

炉心λ内で核反応が起こると、核反応により生じた熱が
冷却拐を加熱し、密度が減少して生じる浮力をライ、ザ
3で拡大し、自然循環力で生じる冷却材の流れで炉心−
の熱が除去される。そして加熱された冷却材は熱交換器
φにおいて熱交換されるO 一方、原子炉の出力制御は、炉心λ内に配された複数本
の制御棒案内管6内に、収容箱7内に収容されている制
御棒/θを挿入し、その挿入量を調節することによシ行
なわれる。
When a nuclear reaction occurs in the reactor core λ, the heat generated by the nuclear reaction heats the cooling chamber, the density decreases, and the buoyant force generated is expanded in the reactor core λ, and the flow of coolant generated by natural circulation forces −
heat is removed. The heated coolant is then heat exchanged in the heat exchanger φ. On the other hand, the output control of the reactor is carried out in a plurality of control rod guide tubes 6 arranged in the reactor core λ, which are housed in the accommodation box 7. This is done by inserting the control rod /θ and adjusting the amount of insertion.

この場合には、まず遠隔操作によシ駆動用モータタを起
動し、両駆動ギヤ7ケを制御棒10の繰出し方向に回転
させる。すると、第2図に示すように両駆動ギヤ/ダ間
に/回転半巻廻された状態で屈曲収容されている制御棒
10が制御棒案内管6内に次第に繰出される。逆に制御
棒案内管6内に挿入収容されている制御棒10を炉心コ
から引抜く場合には・前記駆動用モータタを逆転させる
In this case, first, the drive motor is started by remote control, and both seven drive gears are rotated in the direction in which the control rod 10 is fed out. Then, as shown in FIG. 2, the control rod 10, which is bent and accommodated between both drive gears in a half-rotation state, is gradually drawn out into the control rod guide tube 6. Conversely, when the control rod 10 inserted and housed in the control rod guide tube 6 is to be pulled out from the reactor core, the drive motor is reversed.

しかして、制御棒10の炉心λ内への挿入量が変化し、
これによ#)原子炉の出力が制御される。この際、制御
棒10の炉心コへの挿入、引抜きの速度は・ターミナル
/7i介して駆動用モータタに制御信号を送シ、その回
転数を制御することにより調節される。したかつで、ス
クラム時も駆動用モータタの回転数を増大させることに
より、所定のスクラム時間がりjられる。
Therefore, the amount of insertion of the control rods 10 into the core λ changes,
This controls the power output of the reactor. At this time, the speed at which the control rods 10 are inserted into and withdrawn from the core is adjusted by sending a control signal to the drive motor via the terminal 7i and controlling its rotation speed. In addition, by increasing the rotational speed of the drive motor during a scram, the predetermined scram time can be increased.

また、制御棒10の一定位置での保持は、駆動用モータ
タに内蔵されたブレーキ(図示せず)、制御棒案内管6
、収容箱7内の案内用仕切板/9、および制御棒/θの
ガイドローラ2コにょシ行なわれる。
In addition, the control rod 10 is held in a fixed position by a brake (not shown) built into the drive motor, and by a control rod guide tube 6.
, the guide partition plate/9 in the storage box 7, and the guide roller 2 of the control rod/θ.

なお、停電時にはブレーキがかかるため、制御棒10は
停電直前の位置で保持され、したがってスクラムにはな
らないが、特に緊急停止が必要な場合には、別系統の炉
停止系、例えはポロン注大系等を用いるようにすればよ
い。
In addition, since the brakes are applied during a power outage, the control rods 10 are held in the position immediately before the power outage, and therefore a scram does not occur. However, if an emergency shutdown is particularly necessary, a separate reactor shutdown system, such as a PORON What is necessary is to use a system etc.

一方、制御W案内管6および収容箱7の炉心コへの着脱
は、燃料を除去した炉心格子を上部に引き上げ、その下
部グリッドjに対して遠隔操作によシ行なう。この際、
これらが炉心コや燃料と全く独立構造となっているので
極めて便利でsb、また電線管/2が可撓性を有してい
るため作業が容易である。
On the other hand, the control W guide tube 6 and the storage box 7 are attached to and detached from the reactor core by lifting the core grid from which fuel has been removed upwards, and then remotely controlling the lower grid j. On this occasion,
Since these have a completely independent structure from the reactor core and fuel, it is extremely convenient and work is easy because the electric conduit/2 is flexible.

しかして、屈曲収容可能な制御棒10を用いることによ
シ制御棒/θに関連する部分が小さくなシ、原子炉圧力
容器/内の有効利用および原子炉圧力容器/の小型化が
1」能となる。
Therefore, by using the control rod 10 that can be bent and accommodated, the parts related to the control rod θ are small, the inside of the reactor pressure vessel is effectively utilized, and the reactor pressure vessel is made smaller. Becomes Noh.

また、制御棒10の原子炉圧力容器/への貫通孔が不要
となるので、製作が容易で安価であるとともに、安全性
を向上させることができる。
In addition, since a through hole for the control rod 10 into the reactor pressure vessel is not required, manufacturing is easy and inexpensive, and safety can be improved.

また制御棒駆動機構が簡単で安価であるとともに、動作
が確実で安全であシ、保守が極めて容易である。
In addition, the control rod drive mechanism is simple and inexpensive, and the operation is reliable and safe, and maintenance is extremely easy.

また坤子炉全体の高さを低くすることができ、耐震上お
よび経済上から有利である。また建屋の小型化を図るこ
とができる。
In addition, the height of the entire gonzi furnace can be reduced, which is advantageous from the standpoint of earthquake resistance and economy. Additionally, the building can be made smaller.

なお本発明は前記実施例に限定されるものではなく、制
御棒10の構造を震央したシ形状を棒状にしたり、ある
いは凪動用モータタのt源を電池にしてこれを七−タタ
に組込んだシ、あるいは制御棒10の駆動部を炉心−の
上部に配したシ、さらには制御棒10を巻回収納するの
ではなく折曲げ収納するようにすることも可能でおる。
It should be noted that the present invention is not limited to the above-mentioned embodiments, but the structure of the control rod 10 may be made into a rod shape with the epicenter being a rod shape, or the t source of the calming motor may be made into a battery and this may be incorporated into a seven-tata. Alternatively, it is also possible to arrange the driving part of the control rod 10 at the upper part of the reactor core, and furthermore, it is also possible to arrange the control rod 10 to be stored by bending it instead of winding it up.

また前記実施例においては、自然循環冷却方式の原子炉
を例に採って説明したが、強制循環冷却方式の原子炉に
も同様に適用することができる。
Further, in the above embodiments, a natural circulation cooling type nuclear reactor was used as an example, but the present invention can be similarly applied to a forced circulation cooling type nuclear reactor.

〔発明の効果〕〔Effect of the invention〕

以上説明したように本発明は、屈曲自在な制御棒を用い
、これを収容箱内に屈曲収容するようにしているので、
制御棒駆動機構の原子炉圧力容器内に占める体積を小キ
くシ、原子炉全体の小型化および全体の高さの低減を図
シ、建屋を小型化することができる。まfc構造および
取扱いが簡単であり、保守が容易であるとともに、安全
性を向上させることができる。
As explained above, the present invention uses a bendable control rod, which is bent and accommodated in the storage box.
By reducing the volume occupied by the control rod drive mechanism in the reactor pressure vessel, the entire reactor can be downsized, the overall height can be reduced, and the building can be downsized. The fc structure and handling are simple, maintenance is easy, and safety can be improved.

また原子炉圧力容器内を有効利用できるので、圧力答器
内に熱交換器や蒸気発生器を配置する中小型炉に船に有
効である。
In addition, since the inside of the reactor pressure vessel can be effectively used, it is effective for ships with small and medium-sized reactors in which a heat exchanger and a steam generator are arranged inside the pressure reactor.

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

第1Mは本発明の一実施例を示す自然循環冷却方式の原
子炉の断面図、第2図は収容箱部分の詳細図、第3図は
制御棒の詳細図、第≠図は第3図の仰j面図である。 ハ・・原子炉圧力容器、λ・・・炉心、ψ・・・熱交換
器、j・・・炉心下部グリッド、6・・・制御棒案内管
、7・・・収容箱、り・・・駆動用モータ、10・・・
制御棒、/l・・・送電線、7.2・・・電線管、/l
I・・・駆動ギヤ、/ざ・・・ガイドギヤ、/9・・・
案内用仕切板、20・・・ポイズン板、2/・・・テエ
ーン、n・・・ガイドローラ。 出願人代理人 猪 股 薄 筒1図 第2図 43図 第4図
1M is a cross-sectional view of a natural circulation cooling reactor showing an embodiment of the present invention, FIG. 2 is a detailed view of the containment box, FIG. 3 is a detailed view of the control rod, and ≠ is FIG. FIG. c...Reactor pressure vessel, λ...core, ψ...heat exchanger, j...core lower grid, 6...control rod guide tube, 7...accommodation box, ri... Drive motor, 10...
Control rod, /l...Power transmission line, 7.2...Electric conduit, /l
I...Drive gear, /Za...Guide gear, /9...
Guide partition plate, 20... Poison plate, 2/... Teen, n... Guide roller. Applicant's agent Inomata Thin cylinder Figure 1 Figure 2 Figure 43 Figure 4

Claims (1)

【特許請求の範囲】 /)炉心内に複数個配置された水密構造の制御棒案内管
と、この制御棒案内管の少なくとも上下いずれか一端部
に連結された水密構造の収容箱と、この収容箱内に屈曲
状態で収容され駆動装置によシ前記制御棒案内管内に繰
シ出される制御棒とを具備することを特徴とする原子炉
。 コ)駆動装置の給電ケーブルを、収容箱と原子炉圧力容
器とを水密に連結するチューブ内を通して原子炉圧力容
器外に引出すことを特徴とする特許請求の範囲第1項記
載の原子炉。
[Scope of Claims] /) A plurality of watertight control rod guide tubes arranged in the reactor core, a watertight storage box connected to at least one of the upper and lower ends of the control rod guide tubes, and a watertight storage box connected to at least one end of the control rod guide tube; A nuclear reactor comprising: a control rod that is accommodated in a bent state in a box and is fed out into the control rod guide tube by a drive device. d) The nuclear reactor according to claim 1, characterized in that the power supply cable of the drive device is led out of the reactor pressure vessel through a tube that watertightly connects the storage box and the reactor pressure vessel.
JP59004508A 1984-01-13 1984-01-13 Nuclear reactor Pending JPS60147687A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59004508A JPS60147687A (en) 1984-01-13 1984-01-13 Nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59004508A JPS60147687A (en) 1984-01-13 1984-01-13 Nuclear reactor

Publications (1)

Publication Number Publication Date
JPS60147687A true JPS60147687A (en) 1985-08-03

Family

ID=11585990

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59004508A Pending JPS60147687A (en) 1984-01-13 1984-01-13 Nuclear reactor

Country Status (1)

Country Link
JP (1) JPS60147687A (en)

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