JPH06230164A - Liquid metal cooled nuclear reactor - Google Patents
Liquid metal cooled nuclear reactorInfo
- Publication number
- JPH06230164A JPH06230164A JP50A JP3951193A JPH06230164A JP H06230164 A JPH06230164 A JP H06230164A JP 50 A JP50 A JP 50A JP 3951193 A JP3951193 A JP 3951193A JP H06230164 A JPH06230164 A JP H06230164A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- adjusting rod
- core
- coolant
- liquid level
- 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.)
- Granted
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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【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 cooling nuclear reactor having inherent safety against an abnormal temperature rise of a coolant, and more specifically, a liquid level accompanying an increase in coolant temperature. The present invention relates to a reactor in which the reactor power adjusting rod is directly inserted deep into the core by the action of a float by utilizing the ascent.
【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 Thermometers, flow meters,
Various instruments such as neutron detectors are incorporated to constantly monitor the operating status of the plant. If an abnormality should occur 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, when the main circulation pump stops due to an accident such as a power failure, it immediately switches to a diesel-powered pony motor, but the flow rate decreases. Detecting this, a control rod or 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, and the electromagnet is de-energized by the above-mentioned signal, and it is inserted into the core by its own weight or by using the pressure of 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 is always a process mediated by an electric circuit. As a result, if there is a defect in the process from signal detection to control rod / safety rod insertion due to cable disconnection, short circuit, or loose connectors due to poor quality or aging, or leakage of control gas. If there is a valve malfunction due to, there is a risk that the furnace will not be shut down even if an abnormality is detected. For this reason, the system is becoming more complicated as well as taking sufficient periodical inspections and taking measures such as multiplexing the reactor shutdown mechanism.
【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。An object of the present invention is to provide a liquid metal cooled nuclear reactor which can add safety inherent to the nuclear reactor, enhance the safety and reduce the psychological burden on the operator.
【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 core is supported inside a nuclear reactor vessel by an internal structure, and a low temperature liquid metal coolant flows in through an inlet pipe and is heated through the core. It is premised on a liquid metal cooling reactor having a structure that flows out from the outlet pipe and has a free liquid level inside. And in order to achieve the above object, in the present invention, a liquid surface area limiting mechanism for narrowing the coolant liquid surface is provided in the upper part of the reactor vessel, and a float floating on the liquid surface and the vertical movement of the float cause A reactor power adjusting rod that inserts into and pulls out from the core is provided, and this is a characteristic feature.
【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-described liquid surface area limiting mechanism has, for example, a structure in which an inner cylinder portion and an outer cylinder portion and an annular bottom portion that closes the lower end edges thereof are integrated, and the integral structure is formed from the upper portion of the furnace vessel. It is inserted so that the coolant is guided inside the inner cylindrical portion. In addition, a plurality of adjusting rod supports are hung from the annular float so as to penetrate through the reactor internals, and adjusting rod supports are attached to the adjusting rod supports, and the reactor power adjusting rods are supported by the adjusting rod supports. Then, it is preferable to insert / pull out 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 abnormality occurs in the cooling system and the output system, causing the temperature of the coolant to rise. But it is hard to boil. However, the free liquid level of the reactor rises due to the volume expansion of the coolant as the temperature of the liquid metal rises. The liquid surface area limiting mechanism has a function of expanding 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 in it also rises. The raising of the float drives the adjusting rod connected to it and inserts it into the core. This suppresses reactor reactions. That is,
This means that a unique nuclear reaction suppression mechanism that utilizes physical phenomena is provided without intervening intermediate systems such as electronic circuits.
【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。1 is a structural view showing an embodiment of a liquid metal cooling nuclear reactor according to the present invention, and FIG. 2 is a view taken along the line AA '. 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 to provide a core 14
Is supported. A coolant inlet pipe 16 is connected to a lower side portion of the reactor vessel 10 and an outlet pipe 1 is connected to an upper side portion thereof.
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. An upper core mechanism 20 is located above the core 14, and penetrates a shield plug 22 that closes an upper opening of the reactor vessel 10. Core upper mechanism 20
A control rod drive mechanism 24 and the like are incorporated in the.
【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 liquid surface is provided above the inside of the reactor vessel 10.
In this embodiment, the liquid surface area limiting mechanism 30 includes the inner cylindrical portion 32.
It is a structure in which an outer cylinder part 34 and an annular bottom part 36 that closes the space between the lower end edges of the outer cylinder part 34 and the outer cylinder part 34 are integrated, which is inserted from the upper opening of the reactor vessel 10, and the liquid level 40 is normally the inner cylinder. It is supported so that it is located in the middle portion of the portion 32. The inner tube portion 32 is much larger than the core upper part mechanism 20 and therefore has an annular clearance of a constant width between them.
【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, in the present invention, the liquid surface 4 of the liquid metal coolant is
It has a float 42 that floats at 0, 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 cylinder portion 32 of the liquid surface area limiting mechanism 30 and the core upper portion mechanism 20, and two adjusting rod supports 46 are suspended from a position symmetrical with respect to the center. . Both adjusting rod supports 46 are provided in the groove 1 of the core support plate 13.
It is guided so as to fit into 3a and can freely move only in the vertical direction. Moreover, the internal structure 12
There is an adjusting rod receiver 48 at a position above the
Are integrally fixed to the adjusting rod support 46.
Then, the reactor power adjusting rod 44 is mounted 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 Ｃ
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 the core upper part mechanism 2
It is inserted from the adjusting rod entrance / exit guide 26 that penetrates 0. The material of this reactor power adjusting rod 44 is B 4 C, like other control rods.
It is a neutron absorber such as, after being used for a certain period,
Pull out from the adjusting rod insertion / removal guide 26 and replace 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。Installation of such a reactor vessel internal mechanism is as follows.
It can be done as follows. First, the reactor internal structure 12 is installed in the reactor vessel 10. Next, the adjusting rod support 46 including the float 42 is inserted into the through hole of the in-core structure 12, and the core support plate 13 of the split type is placed on the in-core structure 12 by sandwiching it. Further, the core 14 is installed on the core support plate 13. The liquid surface area limiting mechanism 30 is inserted and fixed in the upper portion of the reactor vessel 10 as described above. Finally, the upper core 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 cylinder portion 32 of the liquid surface area limiting mechanism 30 is determined by the size of the entire reactor vessel 10 and how much the sensitivity of the liquid level change is given. Liquid sodium expands by 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%. Therefore, as a trial calculation, it is assumed that the lower portion of the reactor vessel having an inner diameter of 4 m is filled with sodium having a depth of 15 m. If this sodium is 500 ℃
From 550 to 550 ° C., 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 will have a volume of about 42 due to the volume expansion of sodium.
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 the abnormality of the reactor system, the liquid level rises due to the volume expansion of the liquid metal, and the float 42 moves upward accordingly. The movement of the float 42 directly causes the reactor power adjusting rod 44 to be inserted into the core 14 without an electric signal, and the nuclear reaction of the reactor is suppressed. When the coolant temperature decreases, the position of the float 40 also decreases, the reactor power adjusting rod 44 is pulled out from the core 14, and the nuclear reaction of the reactor approaches the rated value. When the liquid level is below a certain set position, the adjusting rod receiver 48 contacts the reactor internal structure 12,
The reactor power adjusting 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 a preferred embodiment of the present invention has been described in detail above, the present invention is not limited to such a configuration. As the liquid surface area limiting mechanism, a double cylindrical member is incorporated, but the outer periphery of the annular bottom portion is fixed to the inner wall of the reactor vessel so as not to leak as a structure having only an inner cylindrical portion and an annular bottom portion. The structure may be used, or the upper part of the reactor vessel itself may be narrowed. A configuration is also possible in which the reactor power adjusting rod is suspended from the float by a wire via a fulcrum.
【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 the coolant is large, and the temperature rise due to the abnormality of the reactor system is regarded as the abnormal rise of the liquid level, and the float Since the reactor power adjusting rod is directly inserted into the reactor core by the movement, it is possible to suppress the nuclear reaction of the reactor without using an electric signal. In other words, it is possible to obtain a liquid metal cooled nuclear reactor equipped with a unique nuclear reaction suppression mechanism that utilizes physical phenomena excluding the intermediate system. As a result, the inherent safety of the reactor is improved, and the operator's psychological burden can be reduced.
【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 an embodiment of a liquid metal cooling nuclear reactor according to the present invention.
【図２】図１のＡ−Ａ′矢視図。FIG. 2 is a view taken along the line AA ′ of FIG.
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 10 Reactor Vessel 12 Reactor Internal Structure 14 Core 16 Inlet Piping 18 Outlet Piping 30 Liquid Surface Area Limiting Mechanism 40 Liquid Level 42 Float 44 Reactor Output Adjusting Rod 46 Adjusting Rod Support 48 Adjusting Rod Support
Claims (3)
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, a low temperature liquid metal coolant flows in through an inlet pipe, is heated through the core and flows out through an outlet pipe,
In a reactor with a free liquid level inside, a liquid surface area limiting mechanism that narrows the coolant liquid level is provided in the upper part of the reactor vessel, and the float floating on the liquid level and the vertical movement of the float A liquid metal cooled nuclear reactor comprising a reactor power adjusting rod that is inserted into and pulled out from the core.
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. The liquid surface area limiting mechanism includes an inner cylinder portion and an outer cylinder portion,
2. The nuclear reactor according to claim 1, which has a structure in which an annular bottom portion that closes between the lower edges thereof is integrated, and the coolant is guided inside the inner tubular portion.
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 hung from an annular float so as to penetrate through the reactor internals, and adjusting rod supports are attached to the adjusting rod supports, and the reactor output is adjusted by the adjusting rod supports. The reactor according to claim 1 or 2, wherein a rod is supported, and the reactor power adjusting rod is inserted and withdrawn from the lower part of the core.
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 true JPH06230164A (en) | 1994-08-19 |
| JP2831225B2 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) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100836076B1 (en) * | 2006-09-22 | 2008-06-09 | 재단법인서울대학교산학협력재단 | Floating-type nuclear reactor shutdown system |
| ITUA20163716A1 (en) * | 2016-05-04 | 2017-11-04 | Luciano Cinotti | NUCLEAR REACTOR WITH SWITCH-OFF BARS WITH FLOAT INTERVENTION |
| 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 |
-
1993
- 1993-02-03 JP JP5039511A patent/JP2831225B2/en not_active Expired - Fee Related
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100836076B1 (en) * | 2006-09-22 | 2008-06-09 | 재단법인서울대학교산학협력재단 | Floating-type nuclear reactor shutdown system |
| ITUA20163716A1 (en) * | 2016-05-04 | 2017-11-04 | Luciano Cinotti | NUCLEAR REACTOR WITH SWITCH-OFF BARS WITH FLOAT INTERVENTION |
| 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 |
| WO2017191598A1 (en) * | 2016-05-04 | 2017-11-09 | Hydromine Nuclear Energy S.A.R.L. | Nuclear reactor, with control and shutdown rods external the core and to its supporting structures |
| WO2017191597A1 (en) * | 2016-05-04 | 2017-11-09 | Hydromine Nuclear Energy S.A.R.L. | Nuclear reactor, with shutdown rods with intervention by means of float |
| KR20190004779A (en) * | 2016-05-04 | 2019-01-14 | 하이드로마인 뉴클리어 에너지 에스.에이.알.엘. | A reactor having a shutdown rod for intervention by float means |
| CN109478433A (en) * | 2016-05-04 | 2019-03-15 | 水利矿业核能公司 | The nuclear reactor of control-rod and shutdown bar outside the support construction of core and core |
| CN109478432A (en) * | 2016-05-04 | 2019-03-15 | 水利矿业核能公司 | Nuclear reactor with the shutdown bar intervened by means of floating body |
| JP2019516973A (en) * | 2016-05-04 | 2019-06-20 | ハイドロミン ニュクレアル エネルジー ソシエテ ア レスポンサビリテ リミティー | Reactor with out-of-core control rods and stop rods and supporting structure thereof |
| US11101046B2 (en) | 2016-05-04 | 2021-08-24 | Hydromine Nuclear Energy S.A.Rl. | Nuclear reactor, with control and shutdown rods external to the core and core supporting structures |
| CN109478433B (en) * | 2016-05-04 | 2023-06-06 | 水利矿业核能公司 | Nuclear reactor with control rods and shutdown rods outside the core and core support structure |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2831225B2 (en) | 1998-12-02 |
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