JPH05297176A - Nuclear reactor stopping mechanism - Google Patents
Nuclear reactor stopping mechanismInfo
- Publication number
- JPH05297176A JPH05297176A JP4102765A JP10276592A JPH05297176A JP H05297176 A JPH05297176 A JP H05297176A JP 4102765 A JP4102765 A JP 4102765A JP 10276592 A JP10276592 A JP 10276592A JP H05297176 A JPH05297176 A JP H05297176A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- coolant
- core
- curie point
- temperature
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
(57)【要約】
【目的】延長棒と制御棒の間にキュリー点電磁石による
連結手段と軸方向熱膨脹装置を連結して、急激な冷却材
温度上昇が起きるような事故事象に対しても、自己作動
により即応性のある応答で制御棒が炉心に挿入して、冷
却材の温度上昇を抑制して原子炉を停止させる原子炉停
止機構を提供する。
【構成】原子炉容器1の炉心2上部に設置して炉心2内
に昇降自在に設けた制御要素10を冷却材3中にて吊設保
持する炉停止機構20において、原子炉容器1の上部に設
置した延長棒6に取付けたキュリー点電磁石7による連
結手段と、この連結手段に結合して冷却材の温度上昇に
より伸長する軸方向熱膨脹装置21とからなることを特徴
とする。
(57) [Abstract] [Purpose] Even if an accidental event such as a rapid coolant temperature rise occurs, by connecting the Curie point electromagnet connecting means and the axial thermal expansion device between the extension rod and the control rod, (EN) Provided is a reactor shutdown mechanism in which a control rod is inserted into a reactor core by a self-actuating response to suppress a temperature rise of a coolant to shut down the reactor. [Structure] In a reactor stop mechanism 20 for suspending and holding a control element 10 installed above a core 2 of a reactor vessel 1 and vertically movable in the core 2 in a coolant 3, an upper portion of the reactor vessel 1 It is characterized in that it comprises a connecting means by means of the Curie point electromagnet 7 attached to the extension rod 6 installed in the above, and an axial thermal expansion device 21 connected to this connecting means and extending by the temperature rise of the coolant.
Description
【0001】[0001]
【産業上の利用分野】本発明は、高速増殖炉に設置され
る炉停止機構に係り、冷却材の異常温度上昇に際して外
部のセンサー等に依存せず、自己作動して原子炉を確実
にスクラムすることのできる原子炉停止機構に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor stopping mechanism installed in a fast breeder reactor, which is capable of reliably operating a scram by operating by itself without relying on an external sensor or the like when the coolant temperature rises abnormally. Reactor shutdown mechanism that can
【0002】[0002]
【従来の技術】一般に高速増殖炉の炉心では、発生頻度
が10-7〜10-10 /炉年の極めて低確率であることから工
学的には起こることは考えられない炉停止失敗事象が発
生した場合でも、放射性物質が環境に放出されないため
の対策が施されている。しかしながら、このような事象
が発生した場合において従来の原子炉機構では、その事
故影響は原子炉容器内に止まるものの、炉心燃料全体に
わたる損傷が生じる可能性が考えられる。2. Description of the Related Art Generally, in the core of a fast breeder reactor, an occurrence frequency of 10 -7 to 10 -10 / reactor year is extremely low, and a reactor shutdown failure event that is unlikely to occur from an engineering point of view occurs. Even if it does, measures are taken to prevent radioactive materials from being released into the environment. However, when such an event occurs, in the conventional nuclear reactor mechanism, although the accidental impact is stopped in the reactor vessel, damage to the entire core fuel may occur.
【0003】上記の極低頻度事象の1つである流量減少
型の炉停止失敗事象を例にして、炉心損傷に至るまでの
経路を想定する。 (1) 何らかの起因事象の発生により高速炉の1次主循環
ポンプがトリップしたにも係わらず、何らかの信号や手
動によるスクラムができない場合に、炉心燃料での出力
−流量不整合により冷却材の温度は上昇する。A path leading to core damage is assumed by taking an example of a flow stop type failure event of a reactor shutdown, which is one of the extremely low frequency events described above. (1) When the primary main circulation pump of a fast reactor is tripped due to the occurrence of some initiating event, but some signal or manual scrum is not possible, the temperature of the coolant due to the output-flow rate mismatch in the core fuel Rises.
【0004】(2) 冷却材の温度が上昇する過程で、さら
に、スクラムできない場合には、冷却材が沸騰してナト
リウムボイド反応度が挿入され、ボイド反応度が正値で
あった場合は、炉出力が上昇する可能性がある。 (3) 炉出力上昇により燃料ペレットの温度が上昇する
と、炉心全体に行き渡る燃料損傷が生じる可能性があ
る。(2) In the process of increasing the temperature of the coolant, when the scram cannot be further scrambled, the coolant boils and the sodium void reactivity is inserted, and when the void reactivity is a positive value, Furnace power may increase. (3) If the temperature of the fuel pellets rises due to the increase in reactor power, there is a possibility that fuel damage will occur throughout the core.
【0005】そこで従来は、このような冷却材の温度上
昇が生じた場合に、その過度変化を自身で感知しスクラ
ムする自己作動型の炉停止機構が考案されており、自己
作動型炉停止機構の一つとして、特開昭60-66190号公報
にあるような原子炉停止機構が開示されている。この原
子炉停止機構は、図4の概要断面図に示すように、高速
増殖炉の原子炉容器1内には多数の燃料集合体で構成さ
れる炉心2が収納されていて、この炉心2は原子炉容器
1内に充填された冷却材3に浸漬されている。Therefore, conventionally, when such a temperature rise of the coolant occurs, a self-acting type furnace stopping mechanism has been devised which detects the excessive change by itself and scrams. As one of them, a reactor shutdown mechanism as disclosed in JP-A-60-66190 is disclosed. As shown in the schematic cross-sectional view of FIG. 4, this reactor shutdown mechanism has a reactor vessel 1 of a fast breeder reactor in which a core 2 composed of a large number of fuel assemblies is housed. It is immersed in the coolant 3 filled in the reactor vessel 1.
【0006】原子炉容器1の上部開口は原子炉プラグ4
で閉塞されており、この原子炉プラグ4には炉心上部機
構5が設けられ、この炉心上部機構5の下部に延長棒が
取り付けられている。この延長棒は上下に分割されてい
て、上側延長棒6の下部先端に連結手段であるキュリー
点を有する磁性体を材料としたキュリー点電磁石7が設
置され、下側延長棒9の上部先端にはアーマチュア8が
設けてあり、前記キュリー点電磁石7とアーマチュア8
を吸着させた構造となっている。The upper opening of the reactor vessel 1 is a reactor plug 4
The reactor plug 4 is provided with a core upper part mechanism 5, and an extension rod is attached to the lower part of the core upper part mechanism 5. This extension rod is divided into upper and lower parts, and a Curie point electromagnet 7 made of a magnetic material having a Curie point, which is a connecting means, is installed at a lower end of the upper extension rod 6, and a lower extension rod 9 has an upper end. Is provided with an armature 8, and the Curie point electromagnet 7 and the armature 8 are provided.
It has a structure that adsorbs.
【0007】なお、キュリー点電磁石7以下は常時、冷
却材3に浸漬されており、前記下側延長棒9の下部には
制御要素である中性子吸収体10を吊設し、炉心2内には
中性子吸収体10を囲むように下部案内管11が設置されて
いる。この自己作動型の炉停止機構の動作原理につい
て、前記極低頻度事象の1つである流量減少型の炉停止
失敗事象を例にして説明する。The Curie point electromagnets 7 and below are always immersed in the coolant 3, and a neutron absorber 10 which is a control element is hung below the lower extension rod 9, and inside the core 2. A lower guide tube 11 is installed so as to surround the neutron absorber 10. The operating principle of this self-actuating type reactor shutdown mechanism will be described by taking an example of the flow reduction type reactor shutdown failure event, which is one of the extremely low frequency events.
【0008】(a) 何らかの起因事象の発生により高速炉
の1次主循環ポンプがトリップしたにも係わらず、何ら
かの信号や手動によるスクラムができない場合には、炉
心燃料での出力−流量不整合により冷却材3の温度が上
昇する。 (b) 冷却材3の温度上昇により、キュリー点電磁石7の
温度が上昇し、このキュリー点電磁石7の温度がキュリ
ー点を越えるとキュリー点電磁石7は保磁力を失って、
アーマチュア8はキュリー点電磁石7より離脱し、中性
子吸収体10は下部案内管11を通って炉心2内に落下、挿
入される。(A) When the primary main circulation pump of a fast reactor trips due to the occurrence of some cause event but some signal or manual scram is not possible, due to output-flow rate mismatch in the core fuel The temperature of the coolant 3 rises. (b) As the temperature of the coolant 3 rises, the temperature of the Curie point electromagnet 7 rises, and when the temperature of the Curie point electromagnet 7 exceeds the Curie point, the Curie point electromagnet 7 loses its coercive force,
The armature 8 is separated from the Curie point electromagnet 7, and the neutron absorber 10 is dropped and inserted into the core 2 through the lower guide tube 11.
【0009】(c) 中性子吸収体10が炉心2に挿入される
ことにより、負の反応度が投入され、炉出力が低下して
原子炉が安全に停止するため、炉心全体にわたる過熱に
よる燃料損傷を起こさない。 以上のように自己作動型の炉停止機構においては、制御
要素が物理現象だけで異常事態を自身で感知して、安全
に原子炉を停止させる機能を有している。(C) When the neutron absorber 10 is inserted into the core 2, a negative reactivity is introduced, the reactor power is reduced, and the reactor is safely shut down. Therefore, fuel damage due to overheating over the entire core is caused. Does not cause As described above, in the self-actuated reactor shutdown mechanism, the control element has a function of sensing an abnormal situation by itself only by a physical phenomenon and safely shutting down the reactor.
【0010】[0010]
【発明が解決しようとする課題】従来の自己作動型の炉
停止機構においては、図5の冷却材の炉心出口温度変化
特性図で示すように、時刻12で炉停止失敗事象が開始さ
れる。なお、時刻13,13aはキュリー点電磁石7のキュ
リー点到達を、また温度14はキュリー点温度を示し、時
刻15,15aはキュリー点電磁石7の保磁力喪失、および
中性子吸収体10の炉心挿入時刻を示す。In the conventional self-actuated reactor shutdown mechanism, a reactor shutdown failure event is started at time 12 as shown in the characteristic diagram of the temperature change at the core outlet of the coolant in FIG. Times 13 and 13a indicate that the Curie point of the Curie point electromagnet 7 has been reached, and temperature 14 indicates the Curie point temperature. Times 15 and 15a indicate loss of the coercive force of the Curie point electromagnet 7 and the core insertion time of the neutron absorber 10. Indicates.
【0011】さらに、時間16,16aは冷却材3の温度が
キュリー点温度14を越えた時刻13,13aからキュリー点
電磁石7がキュリー点温度14に到達するまでの時間を示
し、実線17は急激な冷却材温度上昇を伴う炉停止失敗事
象におけるの炉心出口温度変化を、一点鎖線18は急激な
冷却材温度上昇を伴わない炉停止失敗事象の場合の炉心
出口温度を表している。Further, the times 16 and 16a indicate the times from the times 13 and 13a when the temperature of the coolant 3 exceeds the Curie point temperature 14 to the time when the Curie point electromagnet 7 reaches the Curie point temperature 14, and the solid line 17 is sharp. The change in the core outlet temperature at the reactor shutdown failure event accompanied by a significant coolant temperature rise, and the dashed-dotted line 18 represents the core outlet temperature in the case of the reactor shutdown failure event not accompanied by the abrupt coolant temperature rise.
【0012】ここで急激な冷却材3の温度を伴う炉停止
失敗事象が発生すると、冷却材3の炉心出口温度は実線
17で示すように、事象開始時刻12から急激な温度上昇が
始まり、この温度上昇に伴いキュリー点電磁石7は昇温
されるが、その温度上昇には時間遅れが生ずる。また急
激な温度上昇を伴わない炉停止失敗事象では、一点鎖線
18で示すように事象開始時刻12から、冷却材3の温度上
昇が始まり、この冷却材3の温度上昇に伴いキュリー点
電磁石7が昇温される。When a reactor shutdown failure event accompanied by a sudden temperature of the coolant 3 occurs, the core outlet temperature of the coolant 3 is indicated by a solid line.
As shown by 17, the temperature rises sharply from the event start time 12, and the Curie point electromagnet 7 is heated with this temperature rise, but there is a time delay in the temperature rise. Also, in the event of a reactor shutdown failure that does not accompany a sudden temperature rise, the alternate long and short dash line
As shown by 18, the temperature rise of the coolant 3 starts from the event start time 12, and the Curie point electromagnet 7 is heated with the temperature rise of the coolant 3.
【0013】冷却材3の温度がキュリー点温度14を越え
て、時間16aが経過するとキュリー点電磁石7はキュリ
ー点温度まで昇温され、キュリー点電磁石7は保磁力を
失い、中性子吸収体10はアーマチュア8および下側延長
棒9と共に、キュリー点電磁石7の吸着面から切り放さ
れ、下部案内管11を通って炉心2に挿入され、この中性
子吸収体10が炉心2に挿入されたことにより、負の反応
度が投入されて、炉出力が低下し、炉心出口温度上昇が
緩和される。When the temperature of the coolant 3 exceeds the Curie point temperature 14 and time 16a elapses, the Curie point electromagnet 7 is heated to the Curie point temperature, the Curie point electromagnet 7 loses its coercive force, and the neutron absorber 10 becomes With the armature 8 and the lower extension rod 9, cut off from the adsorption surface of the Curie point electromagnet 7, inserted into the core 2 through the lower guide tube 11, and by inserting the neutron absorber 10 into the core 2, Negative reactivity is injected to reduce the reactor power and mitigate the core temperature rise.
【0014】しかしながら、実線17および一点鎖線18で
示すように冷却材3の温度がキュリー点温度14に到達し
ても、熱伝達の遅れにより時間16,16aが経過しなけれ
ばキュリー点電磁石7はキュリー点温度に到達せず、そ
のため特に冷却材3の温度上昇が急激な実線17で示す炉
停止失敗事象の場合には、キュリー点電磁石7がキュリ
ー点温度に達する前に冷却材3の温度は点17aで示すよ
うに、かなり高温となり、炉停止が達成する以前に原子
炉内で部分的な燃料破損に至る可能性が考えられ、この
急激な冷却材温度上昇が生じた場合でも、燃料破損に至
らぬ自己作動型の炉停止機構の開発が要望されていた。However, even if the temperature of the coolant 3 reaches the Curie point temperature 14 as shown by the solid line 17 and the alternate long and short dash line 18, if the time 16, 16a does not elapse due to the delay of heat transfer, the Curie point electromagnet 7 is In the case of a reactor shutdown failure event indicated by the solid line 17 in which the Curie point temperature is not reached and therefore the temperature rise of the coolant 3 is sharp, the temperature of the coolant 3 before the Curie point electromagnet 7 reaches the Curie point temperature As indicated by point 17a, the temperature may be so high that it may lead to partial fuel damage within the reactor before the reactor shutdown is reached. Even if this sudden coolant temperature rise occurs, fuel damage may occur. There has been a demand for the development of a self-actuated reactor shutdown mechanism that does not reach the above.
【0015】本発明の目的とするところは、延長棒と制
御棒の間にキュリー点電磁石による連結手段と軸方向熱
膨脹装置を連結して、急激な冷却材温度上昇が起きるよ
うな事故事象に対しても、自己作動により即応性のある
応答で制御棒が炉心に挿入して、冷却材の温度上昇を抑
制して原子炉を停止させる原子炉停止機構を提供するこ
とにある。An object of the present invention is to connect an extension rod and a control rod with a Curie point electromagnet connecting means and an axial thermal expansion device to prevent an accident event in which a rapid coolant temperature rise occurs. Even so, it is an object of the present invention to provide a reactor shutdown mechanism in which control rods are inserted into the core with a quick response due to self-operation to suppress the temperature rise of the coolant and shut down the reactor.
【0016】[0016]
【課題を解決するための手段】原子炉容器の炉心上部に
設置して炉心内に昇降自在に設けた制御要素を冷却材中
にて吊設保持する炉停止機構において、原子炉容器の上
部に設置した延長棒に取付けたキュリー点電磁石による
連結手段と、この連結手段に結合して冷却材の温度上昇
により伸長する軸方向熱膨脹装置とからなることを特徴
とする。[Means for Solving the Problems] In a reactor stop mechanism for suspending and holding a control element, which is installed above the core of a reactor vessel and is vertically movable in the core, in a coolant, the control element is installed above the reactor vessel. It is characterized by comprising a connecting means by means of a Curie point electromagnet attached to an installed extension rod, and an axial thermal expansion device which is connected to the connecting means and extends when the temperature of the coolant rises.
【0017】[0017]
【作用】急激な冷却材温度上昇時には、先ず軸方向熱膨
脹装置の内部に充填された熱膨脹材が昇温した冷却材に
よって加熱膨脹し、ベローズが炉心方向に伸長する。こ
れにより制御要素が炉心に挿入されて、負の反応度が投
入され、炉出力が低下して原子炉が整定状態に移行す
る。When the temperature of the coolant is suddenly increased, the thermal expansion material filled in the axial thermal expansion device is first heated and expanded by the heated coolant, and the bellows is expanded in the core direction. As a result, the control element is inserted into the core, the negative reactivity is input, the reactor power is reduced, and the reactor is settled.
【0018】この間に連結手段のキュリー点電磁石の温
度は十分な余裕をもって冷却材の温度上昇に追従し、前
記軸方向熱膨脹装置による制御要素の炉心挿入では原子
炉停止が不十分な場合で、キュリー点電磁石が保持力を
喪失するキュリー点温度を超すと、前記制御要素を炉心
に落下挿入する。この結果、炉心においては充分な未臨
界体系となり、冷却材の温度上昇が抑制されて炉心損傷
が未然に防止される。During this time, the temperature of the Curie point electromagnet of the connecting means follows the temperature rise of the coolant with a sufficient margin, and when the core shutdown of the control element by the axial thermal expansion device does not sufficiently stop the reactor, the Curie When the point electromagnet exceeds the Curie point temperature at which it loses its coercive force, the control element is dropped into the core. As a result, a sufficient subcritical system is formed in the core, the temperature rise of the coolant is suppressed, and core damage is prevented in advance.
【0019】[0019]
【実施例】本発明の一実施例について図面を参照して説
明する。なお、上記した従来技術と同じ構成部分につい
ては同一符号を付して詳細な説明を省略する。図1は原
子炉停止機構の一部切断拡大正面図で、図2は高速増殖
炉の概要断面図である。An embodiment of the present invention will be described with reference to the drawings. It should be noted that the same components as those of the above-described conventional technique are denoted by the same reference numerals and detailed description thereof will be omitted. FIG. 1 is a partially cutaway enlarged front view of a reactor shutdown mechanism, and FIG. 2 is a schematic sectional view of a fast breeder reactor.
【0020】高速増殖炉の原子炉容器1内には多数の燃
料集合体で構成される炉心2が収納されていて、この炉
心2は原子炉容器1内に充填された冷却材3に浸漬され
ている。また原子炉容器1の上部開口は原子炉プラグ4
で閉塞されており、この原子炉プラグ4には炉心上部機
構5が設けられ、この炉心上部機構5の下部に上側延長
棒6が取付けられている。A reactor core 1 of a fast breeder reactor contains a core 2 composed of a number of fuel assemblies, and the core 2 is immersed in a coolant 3 filled in the reactor container 1. ing. Also, the upper opening of the reactor vessel 1 is the reactor plug 4
The reactor plug 4 is provided with an upper core mechanism 5 and an upper extension rod 6 is attached to the lower part of the upper core mechanism 5.
【0021】さらに、上側延長棒6の下部には自己作動
型の原子炉停止機構20が設置されており、この原子炉停
止機構20を介して制御要素である中性子吸収体10が吊設
されている。また、この中性子吸収体10の下部には炉心
2と、炉心2内で中性子吸収体10を囲むように設けた下
部案内管11が設置されている。Further, a self-actuating reactor stop mechanism 20 is installed below the upper extension rod 6, and a neutron absorber 10 which is a control element is suspended via the reactor stop mechanism 20. There is. Further, a core 2 and a lower guide tube 11 provided so as to surround the neutron absorber 10 in the core 2 are installed below the neutron absorber 10.
【0022】自己作動型の原子炉停止機構20は、図1に
示すように前記上側延長棒6の下部先端に連結手段であ
るキュリー点を有する磁性体を材料としたキュリー点電
磁石7を設置し、このキュリー点電磁石7の吸着面7a
に吸着させたアーマチュア8と下側延長棒9、および軸
方向熱膨張装置21で構成されている。As shown in FIG. 1, the self-actuating nuclear reactor shutdown mechanism 20 is provided with a Curie point electromagnet 7 made of a magnetic material having a Curie point as a connecting means at the lower end of the upper extension rod 6. , The attracting surface 7a of the Curie point electromagnet 7
It is composed of the armature 8 and the lower extension rod 9 and the axial thermal expansion device 21 which are adsorbed on the.
【0023】前記キュリー点電磁石7は、温度がキュリ
ー点温度に至ると保磁力を失う磁性体を材料とする電磁
石で、キュリー点電磁石7の内部にはキュリー点電磁石
7を励起するコイル24が内蔵されていて、アーマチュア
8はキュリー点電磁石7の保磁力によって吸着して、前
記中性子吸収体10を保持している。軸方向熱膨張装置21
は、内部に熱膨脹材22を充填し、この熱膨脹材22の膨脹
により伸長するベローズ23で形成されいる。また原子炉
停止機構20はキュリー点電磁石7を含めて、冷却材3に
浸漬されている。The Curie point electromagnet 7 is an electromagnet made of a magnetic material that loses its coercive force when the temperature reaches the Curie point temperature. Inside the Curie point electromagnet 7, a coil 24 for exciting the Curie point electromagnet 7 is built-in. The armature 8 is adsorbed by the coercive force of the Curie point electromagnet 7 and holds the neutron absorber 10. Axial thermal expansion device 21
Is formed of a bellows 23 which is filled with a thermal expansion material 22 and which expands due to expansion of the thermal expansion material 22. The reactor stop mechanism 20 including the Curie point electromagnet 7 is immersed in the coolant 3.
【0024】次に上記構成による作用について説明す
る。図3は動作特性図で、図3(a)は冷却材の炉心出
口温度を示し、図3(b)は炉心における反応度を、図
3(c)は原子炉出力を表したもので、時刻12が炉停止
失敗事象開始時、時刻25は軸方向熱膨脹装置21による軸
方向膨脹開始時を示し、時刻15はキュリー点電磁石7の
保磁力喪失、および中性子吸収体10の挿入時を表わす。Next, the operation of the above configuration will be described. FIG. 3 is an operation characteristic diagram, FIG. 3 (a) shows the core outlet temperature of the coolant, FIG. 3 (b) shows the reactivity in the core, and FIG. 3 (c) shows the reactor power. Time 12 indicates the start of the reactor failure event, time 25 indicates the start of axial expansion by the axial thermal expansion device 21, and time 15 indicates the loss of coercive force of the Curie point electromagnet 7 and the insertion of the neutron absorber 10.
【0025】ここで定格運転中の原子炉で何らかの起因
事象の発生により高速炉の図示しない1次主循環ポンプ
がトリップしたにも係わらず、何らかの信号や手動によ
るスクラムができない場合を想定すると、炉心燃料での
出力−流量不整合により、図3(a)の曲線26で示すよ
うに、事象開始時刻12から冷却材3の温度は点線矢印26
aの方向に急速に上昇する。Here, assuming that a signal or manual scrum is not possible even though the primary main circulation pump (not shown) of the fast reactor has tripped due to the occurrence of some cause event in the reactor during rated operation, the core is Due to the output-flow rate mismatch in the fuel, the temperature of the coolant 3 from the event start time 12 is shown by the dotted arrow 26 as shown by the curve 26 in FIG.
It rises rapidly in the direction of a.
【0026】この冷却材3の温度上昇に伴い、冷却材3
に浸漬されているキュリー点電磁石7および軸方向熱膨
脹装置21は、冷却材3からの熱伝導により温度が上昇
し、先ず軸方向熱膨脹装置21は内部に充填された熱膨脹
材22の温度が上昇して熱膨脹材22が膨脹する。これに従
いベローズ23が軸方向に伸長し、先端に保持している中
性子吸収体10は下方向に変位して炉心2内に挿入され
る。As the temperature of the coolant 3 rises, the coolant 3
The temperature of the Curie point electromagnet 7 and the axial thermal expansion device 21 immersed in is raised by the heat conduction from the coolant 3, and first, the axial thermal expansion device 21 rises in temperature of the thermal expansion material 22 filled inside. As a result, the thermal expansion material 22 expands. According to this, the bellows 23 extends in the axial direction, and the neutron absorber 10 held at the tip is displaced downward and inserted into the core 2.
【0027】これは図3(b)の曲線27のように、軸方
向膨脹開始時刻25から炉心2に負の反応度が投入され
る。その結果は図5(c)の曲線28で示すように、軸方
向膨脹開始時刻25から炉出力が減少し始める。この出力
減少により、図3(a)の曲線26のように軸方向膨脹開
始時刻25より炉心出口冷却材温度の上昇勾配が点線矢印
26bで示す方向となり、温度上昇率が低下する。As shown by the curve 27 in FIG. 3 (b), the negative reactivity is introduced into the core 2 from the axial expansion start time 25. As a result, as shown by the curve 28 in FIG. 5 (c), the reactor power starts to decrease from the axial expansion start time 25. As a result of this decrease in output, as indicated by the curve 26 in FIG. 3 (a), the rising gradient of the core outlet coolant temperature from the axial expansion start time 25 is indicated by the dotted arrow.
It becomes the direction shown by 26b, and the temperature rise rate decreases.
【0028】しかし、冷却材3の温度がキュリー点電磁
石7のキュリー点温度より高い状態が続くと、キュリー
点電磁石7の温度はキュリー点温度以上となり、保磁力
を失ってキュリー点電磁石7とアーマチュア8は分離
し、自重によってキュリー点電磁石7により保持されて
いたアーマチュア8以下の構造物は自由落下する。However, if the temperature of the coolant 3 continues to be higher than the Curie point temperature of the Curie point electromagnet 7, the temperature of the Curie point electromagnet 7 becomes higher than the Curie point temperature, the coercive force is lost, and the Curie point electromagnet 7 and the armature are lost. 8 separates, and the structure below the armature 8 held by the Curie point electromagnet 7 by its own weight falls freely.
【0029】この落下動作により、中性子吸収体10は下
部案内管11に沿って炉心2内に挿入される。これにより
図3(b)の曲線27で示すように、中性子吸収体10の挿
入時刻15を境に炉心2に対して大きな負の反応度が投入
され、その結果、図3(c)の曲線28のように炉出力が
大幅に減少する。By this dropping operation, the neutron absorber 10 is inserted into the core 2 along the lower guide tube 11. As a result, as shown by the curve 27 in FIG. 3 (b), a large negative reactivity is injected into the core 2 at the time of insertion 15 of the neutron absorber 10, which results in the curve in FIG. 3 (c). Like 28, the furnace power is greatly reduced.
【0030】この出力減少によって冷却材3の温度は、
図3(a)の曲線26のように、時刻15以後は冷却材3の
温度上昇が緩和されて過大な高温にはならず、その後、
充分な未臨界度が確保されて冷却材3の温度は低下し、
安全に原子炉停止状態に移行される。この結果、炉心2
全体にわたる過熱は発生しないので、炉内の高温に起因
する燃料損傷が防止できる。Due to this output reduction, the temperature of the coolant 3 becomes
As shown by the curve 26 in FIG. 3A, after the time 15, the temperature rise of the coolant 3 is moderated and the temperature does not become excessively high.
Sufficient subcriticality is secured and the temperature of the coolant 3 drops,
Safely transition to the reactor shutdown state. As a result, core 2
Since overall overheating does not occur, fuel damage due to high temperature inside the furnace can be prevented.
【0031】[0031]
【発明の効果】以上本発明によれば、応答性が良好な軸
方向熱膨脹装置と負の反応度が十分に得られるキュリー
点電磁石の機構を組み合わせたことにり、従来のキュリ
ー点電磁石に関して課題であった急激な冷却材の温度上
昇が生じる極低頻度事象である原子炉停止失敗事象に対
しても、炉心全体にわたる燃料損傷を防ぐことができ
る。さらに、キュリー点の温度設定に関して裕度が生じ
るので、キュリー点電磁石設計の自由度の拡大ができ、
信頼性の向上とコストダウンの効果がある。As described above, according to the present invention, the axial thermal expansion device having a good responsiveness and the mechanism of the Curie point electromagnet capable of sufficiently obtaining the negative reactivity are combined, and the conventional Curie point electromagnet has a problem. It is possible to prevent fuel damage over the entire core even for a reactor shutdown failure event which is an extremely low frequency event in which a rapid coolant temperature rise occurs. Furthermore, since there is a margin regarding the temperature setting of the Curie point, the degree of freedom in designing the Curie point electromagnet can be expanded,
It has the effects of improving reliability and reducing costs.
【図1】本発明に係る一実施例を示す原子炉停止機構の
一部切断拡大正面図。FIG. 1 is a partially cutaway enlarged front view of a reactor shutdown mechanism showing an embodiment according to the present invention.
【図2】本発明に係る高速増殖炉の概要断面図。FIG. 2 is a schematic sectional view of a fast breeder reactor according to the present invention.
【図3】本発明に係る一実施例の動作特性図(図3
(a)は冷却材の炉心出口温度、図3(b)は炉心にお
ける反応度、図3(c)は原子炉出力)。FIG. 3 is an operational characteristic diagram of one embodiment according to the present invention (see FIG.
(A) is the core outlet temperature of the coolant, FIG. 3 (b) is the reactivity in the core, and FIG. 3 (c) is the reactor power).
【図4】従来の原子炉停止機構を備えた高速増殖炉の概
要断面図。FIG. 4 is a schematic sectional view of a conventional fast breeder reactor equipped with a reactor shutdown mechanism.
【図5】従来の高速増殖炉における冷却材の炉心出口温
度特性図。FIG. 5 is a core outlet temperature characteristic diagram of a coolant in a conventional fast breeder reactor.
1…原子炉容器、2…炉心、3…冷却材、5…炉上部機
構、6…上側延長棒、7…キュリー点電磁石、7a…、
8…アーマチュア、9…下側延長棒、10…中性子吸収
体、11…下部案内管、12…炉停止失敗事象開始時刻、1
3,13a…キュリー点温度到達時刻、14…キュリー点温
度、15,15a…キュリー点電磁石の保磁力喪失時刻と中
性子吸収体の炉心挿入時刻、16,16a…キュリー点電磁
石の昇温時間、17…急激な冷却材温度上昇を伴う炉停止
失敗事象、18…急激な冷却材温度上昇を伴わない炉停止
失敗事象、20…原子炉停止機構、21…軸方向熱膨脹装
置、22…熱膨脹材、23…ベローズ、24…コイル、25…軸
方向膨脹開始時刻、26…冷却材の炉心出口温度曲線、27
…炉心における反応度曲線、28…原子炉出力曲線。DESCRIPTION OF SYMBOLS 1 ... Reactor vessel, 2 ... Reactor core, 3 ... Coolant, 5 ... Reactor upper mechanism, 6 ... Upper extension rod, 7 ... Curie point electromagnet, 7a ...
8 ... Armature, 9 ... Lower extension rod, 10 ... Neutron absorber, 11 ... Lower guide tube, 12 ... Reactor failure event start time, 1
3, 13a ... Curie point temperature reaching time, 14 ... Curie point temperature, 15, 15a ... Curie point electromagnet loss time and neutron absorber core insertion time, 16, 16a ... Curie point electromagnet heating time, 17 … Failure event of reactor shutdown accompanied by sudden temperature rise of coolant, 18… Failure event of reactor shutdown not accompanied by sudden rise of coolant temperature, 20… Reactor shutdown mechanism, 21… Axial thermal expansion device, 22… Thermal expansion material, 23 … Bellows, 24… Coil, 25… Axial expansion start time, 26… Coolant core outlet temperature curve, 27
… Reactor curve in the core, 28… Reactor power curve.
Claims (1)
に昇降自在に設けた制御要素を冷却材中にて吊設保持す
る炉停止機構において、原子炉容器の上部に設置した延
長棒に取付けたキュリー点電磁石による連結手段と、こ
の連結手段に結合して冷却材の温度上昇により伸長する
軸方向熱膨脹装置とからなることを特徴とする原子炉停
止機構。1. A reactor stop mechanism for suspending and holding, in a coolant, a control element which is installed above a core of a reactor vessel and is vertically movable within the core. An extension rod installed above the reactor vessel. A nuclear reactor shutdown mechanism comprising: a connecting means by means of a Curie point electromagnet attached to the shaft; and an axial thermal expansion device which is connected to the connecting means and extends when the temperature of the coolant rises.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4102765A JPH05297176A (en) | 1992-04-22 | 1992-04-22 | Nuclear reactor stopping mechanism |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4102765A JPH05297176A (en) | 1992-04-22 | 1992-04-22 | Nuclear reactor stopping mechanism |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH05297176A true JPH05297176A (en) | 1993-11-12 |
Family
ID=14336282
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4102765A Pending JPH05297176A (en) | 1992-04-22 | 1992-04-22 | Nuclear reactor stopping mechanism |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH05297176A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009186473A (en) * | 2008-02-04 | 2009-08-20 | Westinghouse Electric Co Llc | Cold shutdown apparatus for sodium cooled reactor |
| KR101879428B1 (en) * | 2017-03-23 | 2018-07-17 | 한국전력기술 주식회사 | Secondary shutdown structure for nuclear reactors using sliding doors |
-
1992
- 1992-04-22 JP JP4102765A patent/JPH05297176A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009186473A (en) * | 2008-02-04 | 2009-08-20 | Westinghouse Electric Co Llc | Cold shutdown apparatus for sodium cooled reactor |
| KR101879428B1 (en) * | 2017-03-23 | 2018-07-17 | 한국전력기술 주식회사 | Secondary shutdown structure for nuclear reactors using sliding doors |
| US11488732B2 (en) | 2017-03-23 | 2022-11-01 | Kepco Engineering & Construction Company, Inc. | Secondary shutdown structure of nuclear reactor by using sliding doors |
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