JP2831225B2 - Liquid metal cooled reactor - Google Patents

Liquid metal cooled reactor

Info

Publication number
JP2831225B2
JP2831225B2 JP5039511A JP3951193A JP2831225B2 JP 2831225 B2 JP2831225 B2 JP 2831225B2 JP 5039511 A JP5039511 A JP 5039511A JP 3951193 A JP3951193 A JP 3951193A JP 2831225 B2 JP2831225 B2 JP 2831225B2
Authority
JP
Japan
Prior art keywords
reactor
adjusting rod
core
float
coolant
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 - Fee Related
Application number
JP5039511A
Other languages
Japanese (ja)
Other versions
JPH06230164A (en
Inventor
一男 羽賀
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.)
KAKU NENRYO SAIKURU KAIHATSU KIKO
Original Assignee
KAKU NENRYO SAIKURU KAIHATSU KIKO
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 KAKU NENRYO SAIKURU KAIHATSU KIKO filed Critical KAKU NENRYO SAIKURU KAIHATSU KIKO
Priority to JP5039511A priority Critical patent/JP2831225B2/en
Publication of JPH06230164A publication Critical patent/JPH06230164A/en
Application granted granted Critical
Publication of JP2831225B2 publication Critical patent/JP2831225B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【産業上の利用分野】本発明は、冷却材の異常な温度上
昇に対して固有の安全性を持たせた液体金属冷却原子炉
に関し、更に詳しく述べると、冷却材温度の上昇に伴う
液位上昇を利用して、フロートの作用で原子炉出力調整
棒が直接炉心に深く挿入される形式の原子炉に関するも
のである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a liquid metal-cooled nuclear reactor having inherent safety against an abnormal temperature rise of a coolant, and more particularly, to a liquid level with a rise in coolant temperature. The present invention relates to a reactor of the type in which a reactor power adjusting rod is directly inserted deep into a core by the action of a float using a rise.

【0002】[0002]

【従来の技術】原子炉プラントには、温度計、流量計、
中性子検出計などの各種の計器が組み込まれ、プラント
の運転状況が常に監視されている。そして、万一異常が
発生して、これら計器の信号が、ある設定レベル以上に
なれば、制御回路が作動し、制御棒や安全棒が炉心に挿
入されて、原子炉は停止する。例えば停電などの事故に
より主循環ポンプが停止すると、直ちにディーゼル駆動
のポニーモータに切り換わるが、流量は減少する。それ
を検知して制御棒や安全棒が挿入される。例えば安全棒
の場合、電磁石で吊った状態で保持されており、前記の
信号によって電磁石への通電が切られ、自重で、あるい
は圧縮ガスの圧力を併用して、炉心に挿入する構成が採
用されている。
2. Description of the Related Art A nuclear power plant has a thermometer, a flow meter,
Various instruments such as a neutron detector are installed, and the operating status of the plant is constantly monitored. If an abnormality occurs and the signals of these instruments exceed a certain set level, the control circuit is activated, control rods and safety rods are inserted into the core, and the reactor is shut down. For example, if the main circulation pump stops due to an accident such as a power failure, the system immediately switches to a diesel-driven pony motor, but the flow rate decreases. Upon detecting this, a control rod or a safety rod is inserted. For example, in the case of a safety rod, it is held in a state of being suspended by an electromagnet, the power to the electromagnet is cut off by the above-mentioned signal, and a configuration is adopted in which the safety rod is inserted into the core by its own weight or by using the pressure of the compressed gas together. ing.

【0003】[0003]

【発明が解決しようとする課題】しかし、従来技術で
は、電気回路を媒介としたプロセスが必ず存在してい
る。そのため、もし品質不良や老朽化等に起因するケー
ブルの断線、ショート、コネクタ類の緩みなどによっ
て、信号検出から制御棒、安全棒の挿入までのプロセス
に欠陥が生じていたり、制御用ガスのリークによるバル
ブの不動作等があれば、異常が検出されても炉停止が行
われない恐れも皆無ではない。そのため、十分な定期検
査を実施することのみならず、炉停止機構を多重化する
などの措置を講じており、システムは複雑化している。
However, in the prior art, there always exists a process mediated by an electric circuit. Therefore, if the cable is broken, short-circuited, or the connectors become loose due to poor quality or aging, the process from signal detection to insertion of control rods and safety rods may cause defects, or control gas leakage may occur. Therefore, there is no danger that the furnace will not be stopped even if an abnormality is detected. Therefore, measures such as multiplexing the furnace stop mechanism are taken in addition to performing sufficient periodic inspections, and the system is complicated.

【0004】本発明の目的は、原子炉に固有の安全性を
付加し、安全性を高めて運転員の心理的負担を軽減でき
る液体金属冷却原子炉を提供することである。
[0004] It is an object of the present invention to provide a liquid metal-cooled nuclear reactor that can add inherent safety to the reactor, enhance safety and reduce the psychological burden on operators.

【0005】[0005]

【課題を解決するための手段】本発明は、原子炉容器の
内部で炉心が炉内構造物により支持され、低温の液体金
属冷却材が入口配管から流入して、炉心を通って加熱さ
れて出口配管から流出し、内部に自由液面を有する構造
の液体金属冷却原子炉を前提としている。そして上記目
的を達成するために本発明では、原子炉容器の上部に冷
却材液面を狭める液表面積制限機構を設けると共に、そ
の液面に浮かぶフロートと、該フロートの上下動に伴な
って前記炉心に対して挿入・引抜き動作をする原子炉出
力調整棒を設けており、この点に特徴がある。
According to the present invention, a reactor core is supported by a reactor internal structure inside a reactor vessel, and a low-temperature liquid metal coolant flows from an inlet pipe and is heated through the reactor core. It is premised on a liquid metal-cooled reactor that flows out of the outlet pipe and has a free liquid level inside. In order to achieve the above object, in the present invention, a liquid surface area limiting mechanism for narrowing the coolant level is provided at the upper part of the reactor vessel, and a float floating on the level and a vertical movement of the float are provided. A reactor power adjustment rod that performs insertion and withdrawal operations with respect to the core is provided, which is characterized by this point.

【0006】上記の液表面積制限機構は、例えば、内筒
部と外筒部、及びそれらの下端縁間を塞ぐ円環状底部と
が一体となった構造とし、その一体構造物が炉容器上部
から挿入されていて、冷却材が内筒部の内側に案内され
るように構成する。また円環状のフロートから炉内構造
物を貫通するように複数本の調整棒サポートを吊設し
て、該調整棒サポートに調整棒受けを取り付け、該調整
棒受けで原子炉出力調整棒を支持し、炉心下部から前記
原子炉出力調整棒の挿入・引抜きを行うようにするのが
よい。
The above-mentioned liquid surface area limiting mechanism has, for example, a structure in which an inner cylindrical portion, an outer cylindrical portion, and an annular bottom portion closing between the lower edges thereof are integrated with each other, and the integrated structure is formed from the upper part of the furnace vessel. It is inserted so that the coolant is guided inside the inner cylinder. Also, a plurality of adjustment rod supports are suspended from the annular float to penetrate the internal structure of the reactor, and an adjustment rod receiver is attached to the adjustment rod support, and the reactor power adjustment rod is supported by the adjustment rod receiver. Then, it is preferable to insert and withdraw the reactor power adjusting rod from the lower part of the core.

【0007】[0007]

【作用】液体金属は大気下でも飽和温度が高く(例えば
ナトリウムでは約881℃)、それを冷却材とする原子
炉では冷却系統や出力系統に何らかの異常が生じ冷却材
温度が上昇する事態になっても沸騰し難い。しかし、液
体金属の高温化に伴う冷却材の体積膨張で、原子炉の自
由液面は上昇する。液表面積制限機構は、液体金属の体
積膨張による液位変化を拡大して感度を良くする機能を
果たす。この冷却材の液位上昇に伴って、それに浮いて
いるフロートも上昇する。フロートの上昇は、それに連
結している調整棒を駆動し、該調整棒を炉心内に挿入す
る。これによって原子炉の反応が抑えられる。つまり、
電子回路などの中間系が介在することなく、物理現象を
利用した固有の核反応抑制機構を備えたことになる。
[Function] Liquid metal has a high saturation temperature even in the atmosphere (for example, about 881 ° C for sodium), and in a reactor using it as a coolant, some abnormalities occur in the cooling system and output system, causing the coolant temperature to rise. Even hard to boil. However, the free liquid level of the reactor rises due to the volume expansion of the coolant accompanying the high temperature of the liquid metal. The liquid surface area limiting mechanism has a function of increasing the liquid level change due to the volume expansion of the liquid metal to improve the sensitivity. As the liquid level of the coolant rises, the float floating on it also rises. Raising the float drives an adjustment rod connected thereto and inserts the adjustment rod into the core. This suppresses reactor reactions. That is,
This means that a unique nuclear reaction suppression mechanism utilizing physical phenomena is provided without an intermediate system such as an electronic circuit.

【0008】[0008]

【実施例】図1は本発明に係る液体金属冷却原子炉の一
実施例を示す構造図であり、図2はそのA−A′矢視図
である。原子炉容器10の内部下方に炉内構造物12が
設けられ、その上方で炉心支持板13によって炉心14
が支持されている。原子炉容器10の下方側部には冷却
材の入口配管16が接続され、上方側部には出口配管1
8が接続されていて、低温の液体金属冷却材は入口配管
16から流入し、炉心14を通って加熱され、高温とな
って出口配管18から流出する。炉心14の上方には炉
心上部機構20が位置し、原子炉容器10の上部開口を
塞ぐ遮蔽プラグ22を貫通している。炉心上部機構20
には、制御棒駆動機構24などが組み込まれている。
FIG. 1 is a structural view showing an embodiment of a liquid metal cooled nuclear reactor according to the present invention, and FIG. 2 is a sectional view taken along the line AA 'of FIG. A reactor internal structure 12 is provided below the inside of the reactor vessel 10, and a core support plate 13 is provided above the reactor internal structure 12.
Is supported. A coolant inlet pipe 16 is connected to the lower side of the reactor vessel 10, and an outlet pipe 1 is connected to the upper side.
8 is connected, the low-temperature liquid metal coolant flows in through the inlet pipe 16, is heated through the core 14, becomes hot, and flows out through the outlet pipe 18. A core upper mechanism 20 is located above the core 14, and penetrates a shielding plug 22 that closes an upper opening of the reactor vessel 10. Core upper mechanism 20
Incorporates a control rod drive mechanism 24 and the like.

【0009】さて本発明では原子炉容器10の内部上方
に冷却材液面を狭める液表面積制限機構30を設ける。
この実施例では、液表面積制限機構30は、内筒部32
と外筒部34、及びそれらの下端縁間を塞ぐ円環状底部
36とが一体になった構造体であり、それが原子炉容器
10の上部開口から挿入され、正常時に液面40が内筒
部32の中間部分に位置するような状態で支持されてい
る。内筒部32は、前記の炉心上部機構20よりも遙に
大きく、従って両者の間は一定幅の円環状のクリアラン
スを有する。
In the present invention, a liquid surface area limiting mechanism 30 for narrowing the coolant level is provided above the inside of the reactor vessel 10.
In this embodiment, the liquid surface area limiting mechanism 30 is
And an outer cylinder portion 34, and an annular bottom portion 36 closing the lower edge thereof are integrally formed. The structure is inserted through the upper opening of the reactor vessel 10, and the liquid level 40 is normally set in the inner cylinder. It is supported so as to be located at an intermediate portion of the portion 32. The inner cylinder portion 32 is much larger than the above-described upper core mechanism 20, and therefore has an annular clearance with a certain width between the two.

【0010】更に本発明では、液体金属冷却材の液面4
0に浮かぶフロート42と、該フロート42の上下動に
伴って前記炉心14に対して挿入・引抜き動作する原子
炉出力調整棒44を有する。本実施例では、フロート4
2は、前記液表面積制限機構30の内筒部32と炉心上
部機構20の間に位置する円環状をなし、2本の調整棒
サポート46が中心に対して対称の位置から吊設されて
いる。両調整棒サポート46は、炉心支持板13の溝1
3aに嵌まるようにして案内されて、上下方向にのみ自
由に移動できるようになっている。また炉内構造物12
の上方位置に調整棒受け48があり、該調整棒受け48
は、前記調整棒サポート46に一体に固定されている。
そして、該調整棒受け48の上で原子炉出力調整棒44
が支持されている。
Further, according to the present invention, the liquid surface 4 of the liquid metal coolant is provided.
It has a float 42 floating at zero, and a reactor power adjusting rod 44 that inserts into and pulls out from the core 14 as the float 42 moves up and down. In this embodiment, the float 4
Reference numeral 2 denotes an annular shape located between the inner cylindrical portion 32 of the liquid surface area limiting mechanism 30 and the upper core mechanism 20, and two adjustment rod supports 46 are suspended from positions symmetrical with respect to the center. . Both adjusting rod supports 46 are provided in the grooves 1 of the core support plate 13.
It is guided so as to fit into 3a, and can be freely moved only in the vertical direction. Furnace structure 12
The adjusting rod receiver 48 is located above the adjusting rod receiver 48.
Are integrally fixed to the adjustment rod support 46.
Then, the reactor power adjusting rod 44 is placed on the adjusting rod receiver 48.
Is supported.

【0011】原子炉出力調整棒44は、炉心上部機構2
0を貫く調整棒出入案内26から挿入れさる。この原子
炉出力調整棒44の材質は、他の制御棒と同様、B4
等の中性子吸収材であり、一定期間使用に供した後は、
調整棒出入案内26から引き抜き、新品と交換する。
The reactor power adjusting rod 44 is provided in the upper core mechanism 2.
It is inserted from the adjustment rod entry / exit guide 26 that passes through zero. As with other control rods, the material of the reactor power adjustment rod 44 is B 4 C
Neutron absorber, etc., and after being used for a certain period of time,
Pull out from the adjustment rod access guide 26 and replace it with a new one.

【0012】このような原子炉容器内部機構の設置は、
次のようにして行える。原子炉容器10内に、まず炉内
構造物12を据える。次に、炉内構造物12の貫通孔に
フロート42を含む調整棒サポート46を挿入し、それ
を挾んで分割型の炉心支持板13を炉内構造物12の上
に載せる。更に、炉心支持板13の上に炉心14を設置
する。液表面積制限機構30は、前述のように原子炉容
器10の上部に挿入し固定する。最後に炉心上部機構2
0、遮蔽プラグ22等を取り付ける。
The installation of such a reactor vessel internal mechanism is as follows.
This can be done as follows. First, the reactor internal structure 12 is set in the reactor vessel 10. Next, the adjusting rod support 46 including the float 42 is inserted into the through hole of the furnace internal structure 12, and the divided core support plate 13 is placed on the furnace internal structure 12 with the adjustment rod support 46 interposed therebetween. Further, the core 14 is set on the core support plate 13. The liquid surface area limiting mechanism 30 is inserted and fixed to the upper part of the reactor vessel 10 as described above. Finally, core upper mechanism 2
0, the shield plug 22 and the like are attached.

【0013】液表面積制限機構30の内筒部32をどの
ような形状にするかは、原子炉容器10全体の大きさ
と、どれだけ液位変化の感度を与えるかによって決めら
れる。液体ナトリウムは、温度が100℃上昇すると約
3%体積が膨張する。他方、その間のステンレス鋼の体
積変化は約0.2%である。そこで、試算として、内径
4mの原子炉容器下部を、深さ15mナトリウムが満た
しているとする。もし、このナトリウム全体が500℃
から550℃まで上昇したとすると、ナトリウム体積は
約2.6m3 増加する。液表面積制限機構30によって
原子炉容器内の空間断面積の70%を覆うとすると、前
記のナトリウムの体積膨張によりフロート42は約42
cm上昇する。それによって原子炉出力調整棒44は炉心
14内に約42cm挿入されることになる。
The shape of the inner cylindrical portion 32 of the liquid surface area limiting mechanism 30 is determined by the size of the entire reactor vessel 10 and how much sensitivity of the liquid level change is given. Liquid sodium expands about 3% in volume when the temperature rises by 100 ° C. On the other hand, the volume change of the stainless steel during that time is about 0.2%. Thus, as a trial calculation, it is assumed that the lower part of the reactor vessel having an inner diameter of 4 m is filled with a 15 m-deep sodium. If this whole sodium is 500 ℃
As a result, the sodium volume increases by about 2.6 m 3 . Assuming that the liquid surface area limiting mechanism 30 covers 70% of the space cross-sectional area in the reactor vessel, the float 42 expands to about 42
cm rise. As a result, the reactor power adjusting rod 44 is inserted into the core 14 by about 42 cm.

【0014】原子炉システムの異常により液体金属冷却
材の温度上昇が生じると、液体金属の体積膨張により液
位が上昇し、それに伴ってフロート42が上方へ移動す
る。このフロート42の動きが、電気信号を介さず、そ
のまま原子炉出力調整棒44の炉心14への挿入を引き
起こし、原子炉の核反応が抑えられる。冷却材温度が低
下すれば、フロート40の位置も下がり、原子炉出力調
整棒44が炉心14から引き抜かれ、原子炉の核反応は
定格に近づく。液面が、ある設定位置以下である時に
は、調整棒受け48が炉内構造物12上に接するため、
原子炉出力調整棒44は一定位置で保持される。
When the temperature of the liquid metal coolant rises due to an abnormality in the reactor system, the liquid level rises due to the volume expansion of the liquid metal, and the float 42 moves upward accordingly. This movement of the float 42 causes the reactor power adjusting rod 44 to be inserted into the reactor core 14 without passing through an electric signal, thereby suppressing the nuclear reaction of the reactor. When the coolant temperature decreases, the position of the float 40 also decreases, the reactor power adjusting rod 44 is withdrawn from the core 14, and the nuclear reaction of the reactor approaches the rating. When the liquid level is below a certain set position, the adjusting rod receiver 48 comes into contact with the in-furnace structure 12,
The reactor power adjustment rod 44 is held at a fixed position.

【0015】以上、本発明の好ましい一実施例について
詳述したが、本発明はこのような構成のみに限定される
ものではない。液表面積制限機構として、二重筒状の部
材を組み込んでいるが、内筒部と円環状底部のみを有す
る構造として該円環状底部の外周を原子炉容器の内壁に
漏れがないように固定する構成でもよいし、原子炉容器
自体の上部を狭める構造でもよい。フロートから支点を
介したワイヤで原子炉出力調整棒を吊り下げるような構
成も可能である。
Although the preferred embodiment of the present invention has been described in detail above, the present invention is not limited to such a configuration. As a liquid surface area limiting mechanism, a double cylindrical member is incorporated, but as a structure having only an inner cylindrical portion and an annular bottom portion, the outer periphery of the annular bottom portion is fixed to the inner wall of the reactor vessel without leakage. It may have a configuration or a structure in which the upper part of the reactor vessel itself is narrowed. A configuration in which the reactor power adjusting rod is hung from a float via a fulcrum is also possible.

【0016】[0016]

【発明の効果】本発明は上記のように、冷却材として使
用する液体金属の体積膨張が大きいことを利用し、原子
炉システムの異常による温度上昇を液位の異常上昇とし
て捉えて、フロートの動きにより直接原子炉出力調整棒
を炉心に挿入するものであるから、電気信号を介さず原
子炉の核反応を抑えることができる。つまり中間系を排
除した物理現象を利用した固有の核反応抑制機構を備え
た液体金属冷却原子炉が得られる。これによって原子炉
の固有の安全性が向上し、運転員の心理的負担を軽減す
ることができる。
As described above, the present invention utilizes the fact that the volume expansion of the liquid metal used as a coolant is large, and considers the temperature rise due to an abnormality in the reactor system as an abnormal rise in the liquid level. Since the reactor power adjusting rod is inserted directly into the reactor core by the movement, it is possible to suppress the nuclear reaction of the reactor without using an electric signal. That is, a liquid metal-cooled reactor having a unique nuclear reaction suppression mechanism utilizing a physical phenomenon excluding the intermediate system can be obtained. This improves the inherent safety of the reactor and reduces the psychological burden on operators.

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

【図1】本発明に係る液体金属冷却原子炉の一実施例を
示す概略構成図。
FIG. 1 is a schematic configuration diagram showing one embodiment of a liquid metal cooled nuclear reactor according to the present invention.

【図2】図1のA−A′矢視図。FIG. 2 is a view taken in the direction of arrows AA ′ in FIG. 1;

【符号の説明】[Explanation of symbols]

10 原子炉容器 12 炉内構造物 14 炉心 16 入口配管 18 出口配管 30 液表面積制限機構 40 液面 42 フロート 44 原子炉出力調整棒 46 調整棒サポート 48 調整棒受け DESCRIPTION OF SYMBOLS 10 Reactor vessel 12 Reactor internals 14 Reactor core 16 Inlet piping 18 Outlet piping 30 Liquid surface area limiting mechanism 40 Liquid surface 42 Float 44 Reactor power adjusting rod 46 Adjusting rod support 48 Adjusting rod support

Claims (3)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】 原子炉容器の内部で炉心が炉内構造物に
より支持され、低温の液体金属冷却材が入口配管から流
入して、炉心を通って加熱されて出口配管から流出し、
内部に自由液面を有する形式の原子炉において、原子炉
容器の上部に冷却材液面を狭める液表面積制限機構を設
けると共に、その液面に浮かぶフロートと、該フロート
の上下動に伴なって前記炉心に対して挿入・引抜き動作
する原子炉出力調整棒を設けたことを特徴とする液体金
属冷却原子炉。
1. A reactor core is supported by an internal structure inside a reactor vessel, and a low-temperature liquid metal coolant flows in from an inlet pipe, is heated through the reactor core and flows out from an outlet pipe,
In a reactor of the type having a free liquid level inside, a liquid surface area limiting mechanism for narrowing the coolant level is provided at the top of the reactor vessel, and a float floating on the liquid level and a vertical movement of the float A liquid metal-cooled nuclear reactor, comprising: a reactor power adjusting rod that is inserted into and pulled out of the core.
【請求項2】 液表面積制限機構が、内筒部と外筒部、
及びそれらの下端縁間を塞ぐ円環状底部とが一体となっ
た構造であり、冷却材が内筒部の内側に案内される請求
項1記載の原子炉。
2. A liquid surface area limiting mechanism comprising: an inner cylindrical portion and an outer cylindrical portion;
2. The reactor according to claim 1, wherein the reactor has an integrated structure with an annular bottom portion closing between lower edges thereof, and the coolant is guided inside the inner cylinder portion. 3.
【請求項3】 円環状のフロートから炉内構造物を貫通
するように複数本の調整棒サポートを吊設し、該調整棒
サポートに調整棒受けを取り付け、該調整棒受けで原子
炉出力調整棒を支持し、炉心下部から前記原子炉出力調
整棒の挿入・引抜きを行う請求項1又は2記載の原子
炉。
3. A plurality of adjusting rod supports are suspended from an annular float so as to penetrate the reactor internals, and an adjusting rod receiver is attached to the adjusting rod supports, and the power of the reactor is adjusted by the adjusting rod receivers. The reactor according to claim 1 or 2, wherein the rod is supported, and the reactor power adjusting rod is inserted and withdrawn from a lower part of the core.
JP5039511A 1993-02-03 1993-02-03 Liquid metal cooled reactor Expired - Fee Related JP2831225B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP5039511A JP2831225B2 (en) 1993-02-03 1993-02-03 Liquid metal cooled reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP5039511A JP2831225B2 (en) 1993-02-03 1993-02-03 Liquid metal cooled reactor

Publications (2)

Publication Number Publication Date
JPH06230164A JPH06230164A (en) 1994-08-19
JP2831225B2 true JP2831225B2 (en) 1998-12-02

Family

ID=12555070

Family Applications (1)

Application Number Title Priority Date Filing Date
JP5039511A Expired - Fee Related JP2831225B2 (en) 1993-02-03 1993-02-03 Liquid metal cooled reactor

Country Status (1)

Country Link
JP (1) JP2831225B2 (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100836076B1 (en) * 2006-09-22 2008-06-09 재단법인서울대학교산학협력재단 Floating-type nuclear reactor shutdown system
ITUA20163717A1 (en) * 2016-05-04 2017-11-04 Luciano Cinotti NUCLEAR REACTOR, WITH EXTERNAL CONTROL BARS AND SHUTDOWN TO THE HAZELNUT AND ITS BEARING STRUCTURES
ITUA20163716A1 (en) * 2016-05-04 2017-11-04 Luciano Cinotti NUCLEAR REACTOR WITH SWITCH-OFF BARS WITH FLOAT INTERVENTION

Also Published As

Publication number Publication date
JPH06230164A (en) 1994-08-19

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