JPS5848879B2 - Nuclear reactor control device - Google Patents

Nuclear reactor control device

Info

Publication number
JPS5848879B2
JPS5848879B2 JP51107259A JP10725976A JPS5848879B2 JP S5848879 B2 JPS5848879 B2 JP S5848879B2 JP 51107259 A JP51107259 A JP 51107259A JP 10725976 A JP10725976 A JP 10725976A JP S5848879 B2 JPS5848879 B2 JP S5848879B2
Authority
JP
Japan
Prior art keywords
control rod
guide tube
coolant
nuclear reactor
control device
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
Application number
JP51107259A
Other languages
Japanese (ja)
Other versions
JPS5334094A (en
Inventor
康二 大貫
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 JP51107259A priority Critical patent/JPS5848879B2/en
Publication of JPS5334094A publication Critical patent/JPS5334094A/en
Publication of JPS5848879B2 publication Critical patent/JPS5848879B2/en
Expired 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)

Description

【発明の詳細な説明】 本発明は原子炉特に高速増殖炉の反応度を変えて炉出力
を制御する原子炉の制御装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor control device that controls reactor output by changing the reactivity of a nuclear reactor, particularly a fast breeder reactor.

例えば液体金属冷却形高速増殖炉に使用される制御装置
は、炉心内に配置された案内管と、この案内管内を上下
に移動する制御棒とで構成されている。
For example, a control device used in a liquid metal cooled fast breeder reactor is composed of a guide tube disposed within the reactor core and a control rod that moves up and down within the guide tube.

案内管は、燃料集合体を支持する炉心支持板上に載置さ
れる。
The guide tube is mounted on a core support plate that supports the fuel assembly.

この案内管には下方から上方へ向けて伶却材が流れる。The waste material flows through this guide tube from the bottom to the top.

制御棒は内部に中性子吸収体を具備している。The control rod is equipped with a neutron absorber inside.

この制御棒は炉上方に設けられた制御棒駆動装置によっ
て上下に駆動される。
This control rod is driven up and down by a control rod drive device installed above the reactor.

ところで、制御装置は、隣接する燃料集合体に比べて発
熱量が少なく、最大発熱量に対しても冷却能力を確保す
るために冷却材流量には余裕が持たせてある。
Incidentally, the control device generates less heat than adjacent fuel assemblies, and a margin is provided in the coolant flow rate to ensure cooling capacity even for the maximum amount of heat generated.

このため、冷却材出口の温度は、燃料集合体のそれに比
べて極端に低くなることが考えられる。
Therefore, the temperature at the coolant outlet is considered to be extremely lower than that at the fuel assembly.

この結果、制御棒頂部あるいはその上部に連結する制御
棒駆動機構下部は温度傾斜が激しくなって構造材の熱衝
撃が厳しくなる可能性がある。
As a result, the temperature gradient at the top of the control rod or the lower part of the control rod drive mechanism connected to the top of the control rod becomes severe, and the thermal shock of the structural members may become severe.

すなわち、内側は低温の、外側は高温の冷却材に接する
That is, the inside is in contact with a cold coolant and the outside is in contact with a hot coolant.

本発明は上述の事情に鑑みてなされたもので、冷却材の
流路を変えることによって炉心内への流出を無くシ、よ
って炉心内の冷却材の温度分布の平坦化を図った原子炉
の制御装置を得ることを目的とする。
The present invention was made in view of the above-mentioned circumstances, and is a nuclear reactor that eliminates the flow of coolant into the core by changing the flow path of the coolant, thereby flattening the temperature distribution of the coolant in the core. The purpose is to obtain a control device.

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

図に示す如く本発明の原子炉の制御装置10は制御棒案
内管11と制御棒12とで構成される。
As shown in the figure, a nuclear reactor control device 10 of the present invention is comprised of a control rod guide tube 11 and a control rod 12.

制御棒案内管11は筒状本体13と、この筒状本体13
の下方に形戊された本体13より小径のエントランスノ
ズル14とから成るパイプである。
The control rod guide tube 11 includes a cylindrical body 13 and a cylindrical body 13.
It is a pipe consisting of an entrance nozzle 14 having a smaller diameter than the main body 13 and shaped below the main body 13.

筒状本体13は現在は六角筒状であり、エントランスノ
ズル14は円筒状である。
The cylindrical body 13 currently has a hexagonal cylindrical shape, and the entrance nozzle 14 has a cylindrical shape.

この筒状本体13とエントランスノズル14とからなる
構或体内には、内管16が挿設されている。
An inner tube 16 is inserted into the structure consisting of the cylindrical main body 13 and the entrance nozzle 14.

この内管16は筒状本体13とエントランスノズル14
を小形化したものでエントランスノズル14と筒状本体
13の継き目と、エントランスノズル14の下方内側に
設けられたシールリング17とで筒状本体13内に固定
される。
This inner tube 16 has a cylindrical body 13 and an entrance nozzle 14.
It is fixed in the cylindrical body 13 by a joint between the entrance nozzle 14 and the cylindrical body 13 and a seal ring 17 provided inside the lower part of the entrance nozzle 14.

この内管16は、中央下方にダッシュポット18が形成
される。
A dashpot 18 is formed in the lower center of the inner tube 16.

制御棒12は、内部に中性子吸収体21を内蔵する筒体
で上方にハンドリングヘッド22を、又、下方にエント
ランスノズル23を具備する。
The control rod 12 is a cylindrical body containing a neutron absorber 21 therein, and is provided with a handling head 22 on the upper side and an entrance nozzle 23 on the lower side.

又、制御棒12は中性子吸収体21とハンドリングヘツ
ド22との間に数個の側孔23が穿孔されている。
Further, the control rod 12 has several side holes 23 bored between the neutron absorber 21 and the handling head 22.

この側孔23の上方には円錐状のバツフル板24が介設
される。
A conical baffle plate 24 is interposed above this side hole 23.

前記制御棒案内管13の上端には、制御棒19の横振れ
を規制し冷却材の漏出を抑制する縮小部19がある。
At the upper end of the control rod guide tube 13, there is a reduced portion 19 that restricts the lateral deflection of the control rod 19 and suppresses leakage of coolant.

尚、内管16は、筒状本体13よりも短かい。Note that the inner tube 16 is shorter than the cylindrical main body 13.

又、エントランスノズル14は炉心支持板27によって
垂直に支持される。
Further, the entrance nozzle 14 is vertically supported by a core support plate 27.

このように構成された制御装置10は、炉心支持板27
の下方に形成された高圧プレナム30からエントランス
ノズル14内に冷却材が流入する。
The control device 10 configured in this way has a core support plate 27
Coolant flows into the entrance nozzle 14 from a high pressure plenum 30 formed below.

エントランスノズル14内に流入した冷却材は、図中矢
印で示す如く内管16と筒状本体13で形成される環状
空間を上昇する。
The coolant that has flowed into the entrance nozzle 14 ascends through the annular space formed by the inner tube 16 and the cylindrical body 13, as indicated by the arrow in the figure.

環状空間内を上昇した冷却材は、縮少部19で方向を変
えて側孔23で制御棒12内に入る。
The coolant that has risen within the annular space changes direction at the reduced portion 19 and enters the control rod 12 through the side hole 23 .

制御棒12内に入った冷却材は、バツフル板24でもう
1度方向を変えられて制御棒12内を下降する。
The coolant that has entered the control rod 12 is changed direction once more by the baffle plate 24 and descends within the control rod 12 .

制御棒12内を下降した冷却材はエントランスノズル2
3より外に出て内管16内を下降する。
The coolant that has descended inside the control rod 12 is transferred to the entrance nozzle 2.
3 and descend inside the inner tube 16.

内管16内を下降する冷却材は、ダッシュポット18を
通過して更に降下し、出口31より低圧プレナム32内
へ流出する。
The coolant descending within the inner tube 16 passes through the dashpot 18, further descends, and exits through the outlet 31 into the low pressure plenum 32.

以上説明の様に本発明の原子炉の制御装置は構威されて
いるため、低温の冷却材が燃料集合体で加熱された高温
の冷却材中に流入しなくなり温度分布による熱応力熱衝
撃が機器に作用しない。
As explained above, the nuclear reactor control system of the present invention is structured so that low-temperature coolant does not flow into the high-temperature coolant heated by the fuel assembly, and thermal stress and thermal shock due to temperature distribution occur. Does not affect equipment.

よって機器の設計が楽くになると共に冷却材出口温度の
高温化が図れる。
Therefore, the design of the equipment becomes easier and the coolant outlet temperature can be increased.

尚本発明は高圧プレナム30と低圧プレナム32を変更
して冷却材の流れを逆にしても良い。
It should be noted that the present invention may be implemented by changing the high pressure plenum 30 and the low pressure plenum 32 to reverse the flow of coolant.

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

図は本発明の原子炉の制御装置の一実施例を示す概略縦
断面図である。 11・・・・・・制御棒案内管、12・・・・・・制御
棒、16・・・・・・内管、23・・・・・・側孔、2
4・・・・・・バツフル板。
The figure is a schematic vertical sectional view showing an embodiment of the nuclear reactor control device of the present invention. 11... Control rod guide tube, 12... Control rod, 16... Inner tube, 23... Side hole, 2
4...Batsuful board.

Claims (1)

【特許請求の範囲】[Claims] 1 炉心支持板上に設けられた下部にエントランスノズ
ルを具備する制御棒案内管と、この制御棒案内管内の同
心軸上に設けられ中央にダッシュポットを有する内管と
、前記制御棒案内管頂上から挿入され内管内を上下動す
る制御棒と、この制御棒に内蔵される中性子吸収体と、
この中性子吸収体の上方で前記制御棒の側壁に明けられ
た側孔と、この側孔の上方で前記制御棒内に設けられた
バツフル板と前記制御棒案内管の頂部に設けられ前記制
御棒との相対空間を小さくする縮小部とから構成された
原子炉の制御装置。
1. A control rod guide tube provided on the core support plate and provided with an entrance nozzle at the bottom; an inner tube provided on a concentric axis within this control rod guide tube and having a dashpot in the center; and a control rod guide tube provided at the top of the control rod guide tube. A control rod that is inserted from the inside and moves up and down inside the inner tube, a neutron absorber built into this control rod,
A side hole formed in the side wall of the control rod above the neutron absorber, a buttful plate provided in the control rod above the side hole, and a side hole provided in the top of the control rod guide tube for the control rod. A nuclear reactor control device consisting of a reduction part that reduces the relative space between the
JP51107259A 1976-09-09 1976-09-09 Nuclear reactor control device Expired JPS5848879B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP51107259A JPS5848879B2 (en) 1976-09-09 1976-09-09 Nuclear reactor control device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP51107259A JPS5848879B2 (en) 1976-09-09 1976-09-09 Nuclear reactor control device

Publications (2)

Publication Number Publication Date
JPS5334094A JPS5334094A (en) 1978-03-30
JPS5848879B2 true JPS5848879B2 (en) 1983-10-31

Family

ID=14454505

Family Applications (1)

Application Number Title Priority Date Filing Date
JP51107259A Expired JPS5848879B2 (en) 1976-09-09 1976-09-09 Nuclear reactor control device

Country Status (1)

Country Link
JP (1) JPS5848879B2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5860183A (en) * 1981-10-05 1983-04-09 富士電機システック株式会社 Method and device for controlling temperature in continuous type incinerator

Also Published As

Publication number Publication date
JPS5334094A (en) 1978-03-30

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