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JPH03282397A - Output adjusting device for nuclear reactor - Google Patents

Output adjusting device for nuclear reactor

Info

Publication number
JPH03282397A
JPH03282397A JP2084723A JP8472390A JPH03282397A JP H03282397 A JPH03282397 A JP H03282397A JP 2084723 A JP2084723 A JP 2084723A JP 8472390 A JP8472390 A JP 8472390A JP H03282397 A JPH03282397 A JP H03282397A
Authority
JP
Japan
Prior art keywords
liquid
container
reflector
nuclear reactor
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.)
Pending
Application number
JP2084723A
Other languages
Japanese (ja)
Inventor
Katsumasa Araoka
勝政 荒岡
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 JP2084723A priority Critical patent/JPH03282397A/en
Publication of JPH03282397A publication Critical patent/JPH03282397A/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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To improve movement or transition control over a reflection body, and to stop the operation speedily in emergency and to improve the safety by composing the reflection body of a container wherein liquid reflecting neutrons is injected. CONSTITUTION:In the state of the operation state where the liquid level of the liquid 4 in the container 3 is at the lower end of fuel 2, the liquid 4 is supplied 14 to the hollow part 3a of the container 3 according to the combustion of the fuel 2 to control the maximum position in the reflection (output) area with the height of the liquid level. A driving motor 9 is driven to finely rotate a ball screw 7 engaging a ball screw nut 6 through a speed reducer 8, and the container (reflection body 5) is moved up and down finely to make a short- time fine adjustment for obtaining the best output. Then, if abnormality occurs during operation, a discharge valve 15 is opened automatically to discharge the liquid 3 speedily and the operation of the nuclear reactor can be stopped urgently, so high safety is secured.

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、内部に燃料か収納されている炉容器の周りに
配設した反射体を移動あるいは変位させて出力を制御す
る原子炉の出力調整装置に関する。
[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) The present invention is a method for controlling output by moving or displacing a reflector disposed around a reactor vessel in which fuel is stored. This invention relates to a power adjustment device for a nuclear reactor.

(従来の技術) 研究用や軍事用なとの小型の原子炉においては、燃料を
収納する炉容器の外側に配置した中性子を反射するベリ
リウム等から成る反射体を移動(または変位)させて出
力を制御することが行われている。反射体の形状として
は多数の細い円柱状のものを炉容器の周りに並べたもの
と環状のものとがあり、前者では各円柱状の反射体の回
転角度を変えることにより、後者では炉容器軸方向の位
置を変えることにより制御する。この種の原子炉は研究
用1軍事用といった性格上、ごく限定された係員が原子
炉を運転することを前提としてぃるので、出力を制御す
る反射体の駆動機構も比較的単純な構成、たとえば油圧
駆動とが電動機駆動か用いられている。
(Prior art) In small nuclear reactors such as those for research or military use, a reflector made of beryllium or the like that reflects neutrons is moved (or displaced) placed outside the reactor vessel that stores fuel to output power. is being controlled. There are two types of reflectors: one is a large number of thin cylindrical reflectors arranged around the furnace vessel, and the other is annular. In the former, the rotation angle of each cylindrical reflector is changed, and in the latter, the shape of the reflector is arranged around the furnace vessel. Controlled by changing the axial position. Due to the nature of this type of reactor being for research and military use, it is assumed that only a limited number of personnel will operate the reactor, so the drive mechanism for the reflector that controls the output has a relatively simple structure. For example, hydraulic drive or electric motor drive is used.

しかしながら、この種の原子炉を商業用とする場合には
、研究用あるいは軍事用に比べてはるかに高い安全性が
要求される。すなわち、この種の原子炉では燃料を数年
から千年程度の寿命に設計して反射体の移動(または変
位)制御により穏やかに燃焼させることにしており、も
しも何らかの原因により反射体が許容値よりも大きく移
動(または変位)すると炉心での除熱能力を越える核反
応を引き起こしてしまう恐れがあるので、いかなる事故
・故障、あるいはいかなる誤動作や誤操作によっても反
射体が許容値を越えて移動(または変位)しないようす
る必要がある。
However, when this type of nuclear reactor is used for commercial purposes, much higher safety is required than for research or military use. In other words, in this type of nuclear reactor, the fuel is designed to have a lifespan of several years to a thousand years, and is burnt gently by controlling the movement (or displacement) of the reflector.If for some reason the reflector exceeds the allowable value, If the reflector moves (or is displaced) significantly, it may cause a nuclear reaction that exceeds the heat removal capacity of the reactor core, so any accident or failure, or malfunction or malfunction of the reflector may cause the reflector to move (or displace) beyond the allowable value. (displacement).

第3図は、従来の反射体の移動によって出力を制御する
タイプの原子炉の出力調整装置を示す概略図である。
FIG. 3 is a schematic diagram showing a conventional nuclear reactor power adjustment device of the type that controls power by moving a reflector.

この図に示すように、内部に燃料101を収納した炉容
器100の外側には、中性子を反射してて出力を制御す
るベリリウム合金等から成る環状の反射体102か配置
されており、反射体102の外周面には、ボールネジ1
03と噛み合って反射体102を上下方向に移動させる
ポールネジナツト104と、複数のガイド軸105を挿
通して反射体102を移動自在に支持するリニア軸受1
06が取付けられている。反射体102、ボールネジ1
03、ガイド軸105は原子炉格納容器107内に配設
されている。
As shown in this figure, an annular reflector 102 made of beryllium alloy or the like that reflects neutrons and controls the output is arranged on the outside of a reactor vessel 100 containing fuel 101. On the outer peripheral surface of 102, there is a ball screw 1.
03 to move the reflector 102 in the vertical direction; and a linear bearing 1 that supports the reflector 102 in a movable manner by inserting a plurality of guide shafts 105 therethrough.
06 is installed. Reflector 102, ball screw 1
03, the guide shaft 105 is disposed within the reactor containment vessel 107.

ボールネジ103の両端は、原子炉格納容器107の上
部と下部に設けた軸受は部108a、108b内の軸受
109a、109bで回転自在に支持されており、ボー
ルネジ103の上部には、カップリング110を介して
駆動モータ111と、駆動モータ111の回転を減速す
る減速機112が接続されている。また、ガイド軸10
5の両端は、原子炉格納容器107の上部と下部に設け
た固定部材113a、113bて支持されている。
Both ends of the ball screw 103 are rotatably supported by bearings 109a and 109b provided in the upper and lower parts of the reactor containment vessel 107, and a coupling 110 is installed at the top of the ball screw 103. The drive motor 111 and a speed reducer 112 that reduces the rotation speed of the drive motor 111 are connected through the drive motor 111 . In addition, the guide shaft 10
Both ends of the reactor containment vessel 107 are supported by fixing members 113a and 113b provided at the upper and lower parts of the reactor containment vessel 107, respectively.

従来の原子炉の出力調整装置は上記のように構成されて
おり駆動モータ111の回転駆動力を減速機112、カ
ップリング110を介してボールネジ103に伝達して
ボールネジ103を回転させる。ボールねし103の回
転により噛み合っているポールネジナツト104が上下
動することによって、反射体102がガイド軸105に
ガイドされて上下方向に移動する。このようにして反射
体102か燃料101の燃焼に応じて移動されることに
よって、燃料101の核分裂反応によって放出される中
性子の反射を制御して出力を制御することができる。
A conventional nuclear reactor power adjustment device is configured as described above, and transmits the rotational driving force of the drive motor 111 to the ball screw 103 via the reducer 112 and the coupling 110 to rotate the ball screw 103. When the ball screw 103 rotates and the engaged pole screw nut 104 moves up and down, the reflector 102 is guided by the guide shaft 105 and moves up and down. By moving the reflector 102 in accordance with the combustion of the fuel 101 in this manner, it is possible to control the reflection of neutrons emitted by the nuclear fission reaction of the fuel 101, thereby controlling the output.

この時、燃料101は下部から上部に向って燃焼される
ので、反射体102もそれに応じて移動するように制御
される。
At this time, since the fuel 101 is burned from the bottom to the top, the reflector 102 is also controlled to move accordingly.

また、運転中に最適出力を得るには、反射体102を前
記同様駆動モータ111の回転駆動によって短時間で微
小上下移動させて行う。
Further, in order to obtain the optimum output during operation, the reflector 102 is moved slightly up and down in a short period of time by the rotational drive of the drive motor 111 as described above.

尚、緊急時には、駆動モータ111を高速逆回転させて
反射体102を炉容器100の下方まで移動させ、原子
炉の運転を停止させる。
In an emergency, the drive motor 111 is rotated in reverse at high speed to move the reflector 102 to the lower part of the reactor vessel 100 and stop the operation of the reactor.

(発明が解決しようとする課題) 前記したように従来の原子炉の出力調整装置では、反射
体102の燃料101の燃焼に伴う緩やかな一方向(下
から上)の移動と、最適出力を得るための短時間での微
小上下移動とを、ボールネジ103とポールネジナツト
104の噛み合いによる移動機構で行っていた。
(Problem to be Solved by the Invention) As described above, in the conventional nuclear reactor power adjustment device, the reflector 102 moves slowly in one direction (from bottom to top) as the fuel 101 burns, and the optimal power is obtained. The minute vertical movement in a short period of time for this purpose was performed by a movement mechanism based on the engagement of a ball screw 103 and a pole screw nut 104.

ところか、前記した反射体102の2つの動きは速度、
移動範囲とも大きく異なっているので、駆動モータ11
1の回転制御等にミスが生しると出力が急激に上昇する
恐れかあり、また、緊急時に駆動モータ111の回転方
向を誤ると、反射体102が上方に移動することによっ
て出力が急に上昇する恐れかあり、安全上問題があった
However, the two movements of the reflector 102 described above are speed,
Since the movement range is greatly different, the drive motor 11
If there is a mistake in the rotation control of the drive motor 111, the output may suddenly increase, and if the direction of rotation of the drive motor 111 is incorrect in an emergency, the output may suddenly increase as the reflector 102 moves upward. There was a risk of the water rising, which posed a safety problem.

また、従来のようにボールネジ103とポールネジナツ
ト104の噛み合いによる移動機構では、緊急時に反射
体102を下方に移動させるのに時間かかかり、速やか
に運転を停止することができなかった。
Further, in the conventional moving mechanism based on the engagement of the ball screw 103 and the pole screw nut 104, it takes time to move the reflector 102 downward in an emergency, and the operation cannot be stopped quickly.

本発明は、上記した課題を解決する目的でなされ、反射
体の移動あるいは変位制御を良好に行うことができ、且
つ緊急時には運転を速やかに停止することができる原子
炉の出力調整装置を提供しようとするものである。
The present invention was made for the purpose of solving the above-mentioned problems, and it is an object of the present invention to provide a power adjustment device for a nuclear reactor that can effectively control the movement or displacement of a reflector and can quickly stop operation in an emergency. That is.

[発明の構成] (課題を解決するための手段) 前記した課題を解決するために本発明は、内部に燃料を
収納した炉容器の周りに中性子を炉容器側へ反射する反
射体が配設され、前記反射体を移動あるいは変位させて
出力を制御する原子炉において、内部に中性子を反射す
る液体を注入した容器によって構成される反射体と、前
記容器内へ前記液体を供給する供給手段と、前記容器内
から前記液体を排出する排出手段とを具備したことを特
徴としている。
[Structure of the Invention] (Means for Solving the Problems) In order to solve the above-mentioned problems, the present invention provides a method in which a reflector that reflects neutrons toward the reactor vessel is arranged around a reactor vessel in which fuel is stored inside. In a nuclear reactor in which the output is controlled by moving or displacing the reflector, the reflector is constituted by a container in which a liquid that reflects neutrons is injected, and a supply means for supplying the liquid into the container. , a discharge means for discharging the liquid from inside the container.

また、本発明は、内部に燃料を収納した炉容器の周りに
中性子を炉容器側へ反射する反射体か配設され、前記反
射体を移動あるいは変位させて出力を制御する原子炉に
おいて、内部に液体を注入してその液面上に中性子を反
射する反射部材を浮かべた容器によって構成される反射
体と、前記容器内へ前記液体を供給する供給手段と、前
記容器内から前記液体を排出する排出手段とを具備した
ことを特徴としている。
The present invention also provides a nuclear reactor in which a reflector for reflecting neutrons toward the reactor vessel is disposed around a reactor vessel housing fuel therein, and the output is controlled by moving or displacing the reflector. a reflector constituted by a container in which a liquid is injected and a reflecting member that reflects neutrons is floated on the surface of the liquid; a supply means for supplying the liquid into the container; and a supply means for discharging the liquid from the inside of the container. It is characterized in that it is equipped with a discharge means.

(作用) 本発明によれば、容器内に供給される液体あるいは液体
上の反射部材で反射領域(出力領域)の最大位置を規制
することかできる。
(Function) According to the present invention, the maximum position of the reflection area (output area) can be regulated by the liquid supplied into the container or the reflection member on the liquid.

また、容器内の液体を排出手段で一気に排出することに
より、原子炉を緊急停止することができる。
Further, by discharging the liquid in the container all at once using the discharging means, it is possible to make an emergency shutdown of the nuclear reactor.

(実施例) 以下、本発明を図示の実施例に基づいて詳細に説明する
(Example) Hereinafter, the present invention will be explained in detail based on the illustrated example.

第1図は、本発明の第1実施例に係る原子炉の出力調整
装置を示す概略図である。この図に示すように、内部に
燃料2を収納した炉容器1の外側には、内部に中性子を
反射する液体(例えば水)4が注入される中空部3aを
形成した環状の中性子を反射しない容器3によって構成
される反射体5が配置されている。
FIG. 1 is a schematic diagram showing a nuclear reactor power adjustment device according to a first embodiment of the present invention. As shown in this figure, the outside of a reactor vessel 1 containing fuel 2 has an annular shape that does not reflect neutrons, forming a hollow part 3a into which a liquid (for example, water) 4 that reflects neutrons is injected. A reflector 5 constituted by a container 3 is arranged.

容器3の上部3bには、ボールネ/7と噛み合って容器
3を上下方向に移動させるポールネジナツト6と、複数
(図では1つ)のガイド軸12を挿通して容器3を移動
自在に支持するリニア軸受11が取付けられている。ボ
ールネジ7とガイド軸12は、それぞれ固定部材10a
、10bを介して内部に炉容器1と反射体5を配設した
原子炉格納容器16の上部に取付けられており、ボール
ネジ7の上部には、駆動モータ9と、駆動モータ9の回
転を減速する減速機8が接続されている。
In the upper part 3b of the container 3, a pole screw nut 6 that engages with the ball screw/7 to move the container 3 in the vertical direction and a plurality of guide shafts 12 (one in the figure) are inserted to support the container 3 in a movable manner. A linear bearing 11 is attached. The ball screw 7 and the guide shaft 12 are each fixed member 10a.
, 10b is attached to the upper part of the reactor containment vessel 16 in which the reactor vessel 1 and the reflector 5 are arranged. A speed reducer 8 is connected thereto.

また、容器3の上部には容器3内の中空部3aに液体4
を供給する供給管14が配設され、容器3の下部には容
器3内の中空部3aに注入された液体4を速やかに排出
できる排出弁15を設けた排出管13が配設されている
。供給管14で容器3内の中空部3aに供給される液体
4は、燃料2の燃焼に応じて精度よく少しづつ注入され
、液面の高さで反射領域(出力領域)の最大位置を規制
する。また、排出管13に設けた排出弁15は、緊急時
に自動的に開いて液体4を排出するようになっている。
Further, in the upper part of the container 3, there is a liquid 4 in the hollow part 3a inside the container 3.
A supply pipe 14 for supplying liquid is disposed, and a discharge pipe 13 is disposed at the lower part of the container 3 and equipped with a discharge valve 15 that can quickly discharge the liquid 4 injected into the hollow part 3a of the container 3. . The liquid 4 supplied to the hollow part 3a in the container 3 through the supply pipe 14 is injected little by little with precision as the fuel 2 burns, and the maximum position of the reflection area (output area) is regulated by the height of the liquid level. do. Further, a discharge valve 15 provided in the discharge pipe 13 is configured to automatically open in an emergency to discharge the liquid 4.

尚、図では省略したが、緊急時に容器3内の液体4を全
部排出した後に、復帰時にすぐに再運転ができるように
容器3の上部に液体を任意の流量で注入することかでき
る導入管が配設されている。
Although not shown in the figure, there is an inlet pipe that allows liquid to be injected at any flow rate into the upper part of the container 3 so that after all the liquid 4 in the container 3 has been drained in an emergency, the operation can be resumed immediately upon recovery. is installed.

次に、前記した実施例に係る原子炉の出力調整装置の動
作について説明する。
Next, the operation of the nuclear reactor power adjustment device according to the embodiment described above will be explained.

原子炉の運転開始時には、容器3内に注入される液体4
の液面は燃料2の下端に位置している。
At the start of operation of a nuclear reactor, a liquid 4 is injected into a container 3.
The liquid level is located at the lower end of the fuel 2.

そして、この状態から燃料2の燃焼に合わせて供給管1
4から容器3内の中空部3aに液体4を注入し、液面の
高さで反射領域(出力領域)の最大位置を規制する。
From this state, the supply pipe 1 is
4 into the hollow part 3a in the container 3, and the maximum position of the reflection area (output area) is regulated by the height of the liquid level.

また、最適出力を得るための短時間での微調整は、駆動
モータ9を回転駆動し減速機8を介してポールネジナツ
ト6と噛み合っているボールネジ7を微小回転させて容
器3(反射体5)を、ガイド軸12てしながら微小上下
動させることによって行う。
In addition, fine adjustment in a short time to obtain the optimum output can be achieved by rotationally driving the drive motor 9 to minutely rotate the ball screw 7 that engages with the pole screw nut 6 via the reducer 8. ) by moving the guide shaft 12 up and down slightly.

そして、運転中に原子炉あるいは関連システムに異常が
発生した時には、排出弁15が自動的に開いて容器3内
の液体3を速やかに排出するので、原子炉の運転を緊急
停止することができ、原子炉の運転を緊急停止すること
ができ、高い安全性を確保することができる。
If an abnormality occurs in the reactor or related systems during operation, the discharge valve 15 will automatically open and the liquid 3 in the container 3 will be immediately discharged, making it possible to emergency stop the operation of the reactor. , it is possible to make an emergency stop to the operation of the nuclear reactor, ensuring a high level of safety.

また、緊急時に容器3内の液体4を全部排出した後、復
帰運転する時には不図示の導入管から容器3内に液体4
を任意の流量で注入することにより、すぐに再起動でき
る。
In addition, after all the liquid 4 in the container 3 has been discharged in an emergency, when restarting the operation, the liquid 4 is poured into the container 3 from an inlet pipe (not shown).
can be restarted immediately by injecting it at any flow rate.

第2図は、本発明の第2実施例に係る原子炉の出力調整
装置を示す概略図である。
FIG. 2 is a schematic diagram showing a nuclear reactor power adjustment device according to a second embodiment of the present invention.

本実施例においては、容器3の中空部3aに注入された
液体4の液面上に中性子を反射するベリリウム合金等か
ら成る反射部材20を浮かべた構成である。この場合、
液体4は中性子を反射する必要がなく吸収するものでも
よい。他の構成および動作は前記した実施例と同様であ
る。
In this embodiment, a reflecting member 20 made of beryllium alloy or the like that reflects neutrons is floated on the surface of the liquid 4 injected into the hollow part 3a of the container 3. in this case,
The liquid 4 does not need to reflect neutrons and may absorb them. The other configurations and operations are similar to those of the embodiment described above.

このように本実施例においては、燃料2の燃焼により容
器3内に注入される液体4が増加することによって、液
面上の反射部材20もそれに応じて上方へ移動するので
、反射部材20の高さて反射領域(出力領域)の最大位
置を規制することができる。
In this embodiment, as the liquid 4 injected into the container 3 increases due to the combustion of the fuel 2, the reflecting member 20 on the liquid surface also moves upward accordingly. The maximum position of the reflection area (output area) can be regulated in terms of height.

尚、最適出力を得るための微調整は、前述した駆動モー
タ9により容器3全体も微小上下動させる以外にも種々
方式が考えられる。
It should be noted that various methods can be considered for fine adjustment to obtain the optimum output, other than slightly moving the entire container 3 up and down using the drive motor 9 described above.

例えば、液体4の注入量あるいは排出量を調整して、容
器3全体を微小上下動させるかわりに液面の高さを微小
上下動させてもよい。この時には液体4の注入、排出は
、装置の安全性を考慮して供給管14および排出管13
とは、別系統で設けておくことが望ましい。
For example, the height of the liquid level may be slightly moved up and down by adjusting the injection amount or discharge amount of the liquid 4 instead of moving the entire container 3 up and down. At this time, the liquid 4 is injected and discharged through the supply pipe 14 and the discharge pipe 13 in consideration of the safety of the device.
It is desirable to have a separate system.

[発明の効果] 以上、実施例に基づいて具体的に説明したように本発明
によれば、運転中に原子炉あるいは関連システムに事故
や故障が生じた場合や、誤動作、誤操作等によって出力
制御に異常が発生した場合でも、容器内の液体を速やか
に排出することによって原子炉を緊急停止することがで
きるので、高い安全性を持った原子炉の出力調整装置を
提供することができる。
[Effects of the Invention] As described above in detail based on the embodiments, according to the present invention, output control is possible when an accident or failure occurs in the reactor or related systems during operation, or due to malfunction or erroneous operation. Even if an abnormality occurs in the reactor, the reactor can be brought to an emergency stop by quickly discharging the liquid in the container, so it is possible to provide a highly safe nuclear reactor power adjustment device.

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

第1図は、本発明の第1実施例に係る原子炉の出力調整
装置を示す概略図、第2図は、本発明の第2実施例に係
る原子炉の出力調整装置を示す概略図、第3図は、従来
の原子炉の出力調整装置を示す概略図である。 1・・・炉容器 2・・・燃料 3・・・容器 4・・・液体 5・・・反射体 6・・・ポールネジナツト7・・・ボ
ールネジ 9・・・駆動モータ12・・・ガイド軸 1
3・・・排出管14・・・供給管 15・・・排出弁 16・・・原子炉格納容器
FIG. 1 is a schematic diagram showing a power adjusting device for a nuclear reactor according to a first embodiment of the present invention, and FIG. 2 is a schematic diagram showing a power regulating device for a nuclear reactor according to a second embodiment of the present invention. FIG. 3 is a schematic diagram showing a conventional nuclear reactor power adjustment device. 1... Furnace vessel 2... Fuel 3... Container 4... Liquid 5... Reflector 6... Pole screw nut 7... Ball screw 9... Drive motor 12... Guide Axis 1
3... Discharge pipe 14... Supply pipe 15... Discharge valve 16... Reactor containment vessel

Claims (2)

【特許請求の範囲】[Claims] (1)内部に燃料を収納した炉容器の周りに中性子を炉
容器側へ反射する反射体が配設され、前記反射体を移動
あるいは変位させて出力を制御する原子炉において、内
部に中性子を反射する液体を注入した容器によって構成
される反射体と、前記容器内へ前記液体を供給する供給
手段と、前記容器内から前記液体を排出する排出手段と
を具備したことを特徴とする原子炉の出力調整装置。
(1) In a nuclear reactor, a reflector that reflects neutrons toward the reactor vessel is arranged around a reactor vessel that stores fuel inside, and the output is controlled by moving or displacing the reflector. A nuclear reactor comprising a reflector constituted by a container filled with a reflective liquid, a supply means for supplying the liquid into the container, and a discharge means for discharging the liquid from inside the container. output adjustment device.
(2)内部に燃料を収納した炉容器の周りに中性子を炉
容器側へ反射する反射体が配設され、前記反射体を移動
あるいは変位させて出力を制御する原子炉において、内
部に液体を注入してその液面上に中性子を反射する反射
部材を浮かべた容器によって構成される反射体と、前記
容器内へ前記液体を供給する供給手段と、前記容器内か
ら前記液体を排出する排出手段とを具備したことを特徴
とする原子炉の出力調整装置。
(2) In a nuclear reactor, a reflector that reflects neutrons toward the reactor vessel is arranged around a reactor vessel that stores fuel inside, and the output is controlled by moving or displacing the reflector. A reflector constituted by a container in which a reflecting member for reflecting neutrons is floated on the surface of the liquid that is injected, a supply means for supplying the liquid into the container, and a discharge means for discharging the liquid from the inside of the container. A nuclear reactor output adjustment device characterized by comprising:
JP2084723A 1990-03-30 1990-03-30 Output adjusting device for nuclear reactor Pending JPH03282397A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2084723A JPH03282397A (en) 1990-03-30 1990-03-30 Output adjusting device for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2084723A JPH03282397A (en) 1990-03-30 1990-03-30 Output adjusting device for nuclear reactor

Publications (1)

Publication Number Publication Date
JPH03282397A true JPH03282397A (en) 1991-12-12

Family

ID=13838606

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2084723A Pending JPH03282397A (en) 1990-03-30 1990-03-30 Output adjusting device for nuclear reactor

Country Status (1)

Country Link
JP (1) JPH03282397A (en)

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WO2009038179A1 (en) * 2007-09-21 2009-03-26 Kabushiki Kaisha Toshiba Reflector control type fast reactor
WO2017059360A1 (en) * 2015-09-30 2017-04-06 Terrapower, Llc Neutron reflector assembly for dynamic spectrum shifting
CN107924721A (en) * 2015-07-29 2018-04-17 原子能技术公司 The nuclear reactor of bolt and nut driving with reactor core reaction controlling component
US10665356B2 (en) 2015-09-30 2020-05-26 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
US10741293B2 (en) 2016-05-02 2020-08-11 Terrapower, Llc Molten fuel reactor cooling and pump configurations
US10867710B2 (en) 2015-09-30 2020-12-15 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
US10923238B2 (en) 2016-11-15 2021-02-16 Terrapower, Llc Direct reactor auxiliary cooling system for a molten salt nuclear reactor
US11075015B2 (en) 2018-03-12 2021-07-27 Terrapower, Llc Reflectors for molten chloride fast reactors
US11075013B2 (en) 2016-07-15 2021-07-27 Terrapower, Llc Removing heat from a nuclear reactor by having molten fuel pass through plural heat exchangers before returning to core
US11145424B2 (en) 2018-01-31 2021-10-12 Terrapower, Llc Direct heat exchanger for molten chloride fast reactor
US11170901B2 (en) 2014-12-29 2021-11-09 Terrapower, Llc Fission reaction control in a molten salt reactor
US11276503B2 (en) 2014-12-29 2022-03-15 Terrapower, Llc Anti-proliferation safeguards for nuclear fuel salts
US11373765B2 (en) 2016-08-10 2022-06-28 Terrapower, Llc Electro-synthesis of uranium chloride fuel salts
US11728052B2 (en) 2020-08-17 2023-08-15 Terra Power, Llc Fast spectrum molten chloride test reactors
US11881320B2 (en) 2019-12-23 2024-01-23 Terrapower, Llc Molten fuel reactors and orifice ring plates for molten fuel reactors
US12049408B2 (en) 2018-09-14 2024-07-30 Terrapower, Llc Corrosion-resistant coolant salt and method for making same
US12424343B2 (en) 2014-12-29 2025-09-23 Terrapower Isotopes, Llc Separation of actinium from an irradiated source material including thorium

Cited By (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2009038179A1 (en) * 2007-09-21 2009-03-26 Kabushiki Kaisha Toshiba Reflector control type fast reactor
US11170901B2 (en) 2014-12-29 2021-11-09 Terrapower, Llc Fission reaction control in a molten salt reactor
US12424343B2 (en) 2014-12-29 2025-09-23 Terrapower Isotopes, Llc Separation of actinium from an irradiated source material including thorium
US12154697B2 (en) 2014-12-29 2024-11-26 Terrapower, Llc Anti-proliferation safeguards for nuclear fuel salts
US11276503B2 (en) 2014-12-29 2022-03-15 Terrapower, Llc Anti-proliferation safeguards for nuclear fuel salts
CN107924721A (en) * 2015-07-29 2018-04-17 原子能技术公司 The nuclear reactor of bolt and nut driving with reactor core reaction controlling component
CN107924721B (en) * 2015-07-29 2020-03-10 原子能技术公司 Screw-Nut Driven Nuclear Reactor with Core Reaction Control Components
WO2017059360A1 (en) * 2015-09-30 2017-04-06 Terrapower, Llc Neutron reflector assembly for dynamic spectrum shifting
US10665356B2 (en) 2015-09-30 2020-05-26 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
US10734122B2 (en) 2015-09-30 2020-08-04 Terrapower, Llc Neutron reflector assembly for dynamic spectrum shifting
US10867710B2 (en) 2015-09-30 2020-12-15 Terrapower, Llc Molten fuel nuclear reactor with neutron reflecting coolant
US11798694B2 (en) 2015-09-30 2023-10-24 Terrapower, Llc Molten fuel nuclear reactor
US10741293B2 (en) 2016-05-02 2020-08-11 Terrapower, Llc Molten fuel reactor cooling and pump configurations
US11367536B2 (en) 2016-05-02 2022-06-21 Terrapower, Llc Molten fuel reactor thermal management configurations
US11075013B2 (en) 2016-07-15 2021-07-27 Terrapower, Llc Removing heat from a nuclear reactor by having molten fuel pass through plural heat exchangers before returning to core
US11373765B2 (en) 2016-08-10 2022-06-28 Terrapower, Llc Electro-synthesis of uranium chloride fuel salts
US11488731B2 (en) 2016-11-15 2022-11-01 Terrapower, Llc Direct reactor auxiliary cooling system for a molten salt nuclear reactor
US10923238B2 (en) 2016-11-15 2021-02-16 Terrapower, Llc Direct reactor auxiliary cooling system for a molten salt nuclear reactor
US11145424B2 (en) 2018-01-31 2021-10-12 Terrapower, Llc Direct heat exchanger for molten chloride fast reactor
US11791057B2 (en) 2018-03-12 2023-10-17 Terrapower, Llc Reflectors for molten chloride fast reactors
US11075015B2 (en) 2018-03-12 2021-07-27 Terrapower, Llc Reflectors for molten chloride fast reactors
US12049408B2 (en) 2018-09-14 2024-07-30 Terrapower, Llc Corrosion-resistant coolant salt and method for making same
US11881320B2 (en) 2019-12-23 2024-01-23 Terrapower, Llc Molten fuel reactors and orifice ring plates for molten fuel reactors
US11728052B2 (en) 2020-08-17 2023-08-15 Terra Power, Llc Fast spectrum molten chloride test reactors

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