JPH03243891A - Emergency reactor core shutdown mechanism - Google Patents
Emergency reactor core shutdown mechanismInfo
- Publication number
- JPH03243891A JPH03243891A JP2040835A JP4083590A JPH03243891A JP H03243891 A JPH03243891 A JP H03243891A JP 2040835 A JP2040835 A JP 2040835A JP 4083590 A JP4083590 A JP 4083590A JP H03243891 A JPH03243891 A JP H03243891A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- neutron absorber
- cooling material
- storage chamber
- holding means
- 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
- 239000006096 absorbing agent Substances 0.000 claims abstract description 26
- 239000000446 fuel Substances 0.000 claims abstract description 24
- 239000011261 inert gas Substances 0.000 claims abstract description 15
- 230000002159 abnormal effect Effects 0.000 claims abstract description 12
- 238000005192 partition Methods 0.000 claims abstract description 6
- 239000002826 coolant Substances 0.000 claims description 18
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract description 5
- 239000007789 gas Substances 0.000 abstract description 5
- 229910052708 sodium Inorganic materials 0.000 abstract description 5
- 239000011734 sodium Substances 0.000 abstract description 5
- 239000007788 liquid Substances 0.000 abstract description 4
- 230000004043 responsiveness Effects 0.000 abstract description 3
- 238000001816 cooling Methods 0.000 abstract 6
- 239000000463 material Substances 0.000 abstract 6
- 239000003758 nuclear fuel Substances 0.000 abstract 1
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 3
- 229910052796 boron Inorganic materials 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000005259 measurement Methods 0.000 description 3
- 230000005856 abnormality Effects 0.000 description 2
- 238000001514 detection method Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000000696 magnetic material Substances 0.000 description 2
- 230000007257 malfunction Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000004044 response Effects 0.000 description 2
- 238000004364 calculation method Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 229910052735 hafnium Inorganic materials 0.000 description 1
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 description 1
- 238000005339 levitation Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
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
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は高速増殖炉の炉心を緊急に停止する異常温度自
己検出作動型の緊急炉心停止機構に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to an emergency core shutdown mechanism of an abnormal temperature self-detection type that shuts down the core of a fast breeder reactor in an emergency.
従来、高速増殖炉においては、原子炉の起動、停止およ
び出力の制御は制御棒で行っている。制御棒には調整棒
と後備炉停止棒があり、通常の起動、停止および出力制
御は調整棒が行い、緊急停止時には調整棒からなる系統
と後備炉停止棒からなる系統の緊急炉停止系が同時に働
いて、中性子吸収体を炉心燃料領域に装備して原子炉を
停止させるようにしている。Conventionally, in fast breeder reactors, control rods are used to start, stop, and control the output of the reactor. The control rod has an adjustment rod and a backup reactor shutdown rod.The adjustment rod performs normal startup, shutdown, and output control, and in the event of an emergency shutdown, an emergency reactor shutdown system consisting of a system consisting of the adjustment rod and a system consisting of the backup reactor shutdown rod is activated. Working simultaneously, neutron absorbers are installed in the core fuel region to shut down the reactor.
第4図は従来の後備炉停止棒による緊急炉心停止機構に
おける原子炉炉心部の説明図で、図中、20は炉心燃料
領域、21は後備炉停止棒である。FIG. 4 is an explanatory diagram of a nuclear reactor core in a conventional emergency core shutdown mechanism using backup reactor shutdown rods. In the figure, 20 is a core fuel region and 21 is a backup reactor shutdown rod.
図に示すように、中性子吸収体を内蔵して後備炉停止棒
21を炉心燃料領域20の上方に制御棒駆動装置(図示
せず)で吊り下げておき、炉心燃料領域20において異
常温度上昇が生じた時に後備炉停止枠の制御棒駆動装置
との連結を外して炉心燃料領域20に装荷し、周囲の中
性子を減速、吸収して、炉心燃料領域20の温度上昇を
抑制すると共に、原子炉を緊急に停止する。As shown in the figure, a backup reactor shutdown rod 21 with a built-in neutron absorber is suspended above the core fuel region 20 by a control rod drive device (not shown), and an abnormal temperature rise in the core fuel region 20 is prevented. When this occurs, the backup reactor shutdown frame is disconnected from the control rod drive device and loaded into the core fuel region 20, decelerating and absorbing surrounding neutrons, suppressing the temperature rise in the core fuel region 20, and shutting down the reactor. stop immediately.
この場合、制御棒駆動装置に後備炉停止枠21を保持す
るためには電磁石を利用した電磁クラッチ、またはキュ
ーり温度を有する永久磁石等が用いられ、緊急停止信号
により電磁石を消磁するか、又は冷却材のキューり点を
越える異常温度上昇により永久磁石を非磁性体に変化さ
せて、後備炉停止枠21の保持を解除するようにしてい
る。In this case, an electromagnetic clutch using an electromagnet or a permanent magnet having a cue temperature is used to hold the back-up reactor shutdown frame 21 in the control rod drive device, and the electromagnet is demagnetized by an emergency stop signal, or The permanent magnet is changed into a non-magnetic material due to an abnormal temperature rise exceeding the coolant temperature point, and the holding of the standby reactor shutdown frame 21 is released.
このように従来、原子炉を緊急に停止するには制御棒駆
動装置に離脱可能な後備炉停止枠を取付け1.異常温度
上昇、または異常温度上昇による緊急停止信号等により
中性子吸収体を内蔵した後備炉停止枠を炉心燃料領域に
装荷するものである。Conventionally, in order to stop a nuclear reactor in an emergency, a removable back-up reactor shutdown frame was attached to the control rod drive device.1. A back-up reactor shutdown frame containing a built-in neutron absorber is loaded into the core fuel area in response to an abnormal temperature rise or an emergency shutdown signal due to an abnormal temperature rise.
後備炉停止枠を電磁クラッチで保持するものにあっては
、原子炉運転時に計測制御機器の健全な維持、人為的不
作動の防止に努める必要性を有し、キューり温度を有す
る永久磁石で保持するものにあっては、非磁性体になる
までに時間を要し、応答性が悪い欠点がある。For those that hold the back-up reactor shutdown frame with an electromagnetic clutch, there is a need to maintain the soundness of measurement and control equipment during reactor operation and to prevent artificial inoperation, and it is necessary to use permanent magnets with a certain temperature. Those that retain the magnetic material have the disadvantage that it takes time to become non-magnetic and the responsiveness is poor.
さらに、制御棒駆動装置に吊り下げられた後備炉停止枠
は横揺れが生じゃすく、連結部から切り離され、誤動作
の可能性がある。Furthermore, the standby reactor shutdown frame, which is suspended from the control rod drive, is subject to lateral sway and may become disconnected from its connections, potentially resulting in malfunction.
本発明は上記課題を解決するためのもので、信頼性、連
応性、耐震性に優れ、緊急炉心停止に係る計測制御機器
の規模を縮小し、信頼性を向上すると共に、製作および
建設コストを低減化することのできる緊急炉停止機構を
提供することを目的とする。The present invention is intended to solve the above problems, and has excellent reliability, coordination, and earthquake resistance, reduces the scale of measurement and control equipment related to emergency core shutdown, improves reliability, and reduces manufacturing and construction costs. The purpose is to provide an emergency reactor shutdown mechanism that can reduce the
そのために本発明の緊急炉停止機構は、冷却材が流入可
能な収納室を下端部に有する炉停止棒と、該収納室内に
配置され、中性子吸収体を保持する不活性ガスを収納し
た下端開放の中性子吸収体保持手段とを備え、異常温度
上昇による不活性ガスの膨張により中性子吸収体保持手
段内の冷却材を流出させ、中性子吸収体保持手段を浮上
させて中性子吸収体を炉心燃料領域へ移動させることを
特徴とする。To this end, the emergency reactor shutdown mechanism of the present invention includes a reactor shutdown rod that has a storage chamber at its lower end into which coolant can flow, and an open lower end that is disposed within the storage chamber and contains an inert gas that holds a neutron absorber. A neutron absorber holding means is provided, and the coolant in the neutron absorber holding means is caused to flow out due to the expansion of the inert gas due to an abnormal temperature rise, and the neutron absorber holding means is levitated to move the neutron absorber into the reactor core fuel region. It is characterized by being moved.
本発明の緊急炉心停止機構は、冷却材が流入可能な収納
室内にボロンのような中性子吸収体を保持した内筒内に
不活性ガスを入れ、異常温度上昇による不活性ガスの熱
膨張により内筒内の冷却材を押し出し、その結果生ずる
内筒の浮上により中性子吸収体を炉心燃料領域へ移動さ
せて原子炉を停止させるものであり、温度上昇によるガ
ス空間の熱膨張という物理現象を利用するため、設計が
容易になるとともに、炉停止の方法を多様化させ、信頼
性及び応答性を向上させることが可能となる。In the emergency core shutdown mechanism of the present invention, an inert gas is placed in an inner cylinder that holds a neutron absorber such as boron in a storage chamber into which coolant can flow. This system pushes out the coolant inside the cylinder and uses the resulting levitation of the inner cylinder to move the neutron absorber to the core fuel area and shut down the reactor, making use of the physical phenomenon of thermal expansion of the gas space due to temperature rise. Therefore, the design becomes easier, and it becomes possible to diversify reactor shutdown methods and improve reliability and responsiveness.
以下、実施例を図面を参照して説明する。 Examples will be described below with reference to the drawings.
第1図は本発明による緊急炉心停止機構の一実施例を示
す側面図、第2図および第3図はそれぞれ第1図のAA
′断面およびBB’断面を示す図で、1は内筒、2は支
柱、3は中性子吸収体、4は収納容器、5は支持棒、6
は蓋、7は不活性ガス、8は炉停止棒ラッパ管、9は収
納室、1oは隔壁、11は底板、12は流通孔、13は
冷却材、14は上部ブレナム、15は炉心燃料集合体で
ある。FIG. 1 is a side view showing one embodiment of the emergency core shutdown mechanism according to the present invention, and FIGS. 2 and 3 are AA of FIG. 1, respectively.
' cross section and BB' cross section, 1 is an inner cylinder, 2 is a column, 3 is a neutron absorber, 4 is a storage container, 5 is a support rod, 6
is the lid, 7 is the inert gas, 8 is the reactor stop rod wrapper tube, 9 is the storage chamber, 1o is the bulkhead, 11 is the bottom plate, 12 is the circulation hole, 13 is the coolant, 14 is the upper blemish, 15 is the reactor core fuel assembly It is the body.
図において、後備炉停止枠の外装をなす炉停止棒ラッパ
管8は周囲に配置された炉心燃料集合体15と同一形状
の六角形の外形をなしている。下部には冷却材13とし
ての液体す)IJウムの通る1個または複数の流通孔1
2を有する隔壁1oと底板11で仕切られた収納室9が
設けられている。In the figure, the reactor shutdown rod wrapper tube 8 forming the exterior of the backup reactor shutdown frame has a hexagonal outer shape that is the same as the core fuel assembly 15 disposed around it. The lower part has one or more flow holes 1 through which liquid as a coolant 13 passes.
A storage chamber 9 is provided which is partitioned by a partition wall 1o and a bottom plate 11.
隔壁10は後述するような位置に取付けられている。The partition wall 10 is attached at a position as will be described later.
円筒状の内筒1は収納室9に上下に自由に移動すること
ができるよう炉心燃料領域2oよりも長尺でその気密構
造になるように蓋6が設けられ、下端は開放され、内面
に固定された3本の中空の支柱2が突き出ていて、底板
11の上に安定に置かれることができる。また、内筒1
の下端にボロンまたはハフニウム等の中性子吸収体3を
入れた中空の収納容器4が支柱2に支持棒5で取付けら
れている。また、上述の各構成品は何れもステンレスで
作られている。The cylindrical inner cylinder 1 is longer than the core fuel area 2o so that it can move freely up and down into the storage chamber 9, and is provided with a lid 6 to create an airtight structure. Three fixed hollow columns 2 protrude and can be stably placed on the bottom plate 11. In addition, the inner cylinder 1
A hollow storage container 4 containing a neutron absorber 3 such as boron or hafnium is attached to the column 2 by a support rod 5 at the lower end thereof. Further, each of the above-mentioned components is made of stainless steel.
隔壁10は内筒1が上方に移動して蓋6が接触したとき
に収納容器4が炉心燃料領域20のほぼ中央の高さにな
るような位置、すtヨわも蓋6との距離が炉心燃料領域
20の高さの略1/2に等しい位置に設けられである。The partition wall 10 is located at a position such that when the inner cylinder 1 moves upward and the lid 6 comes into contact with it, the storage container 4 is at a height approximately at the center of the core fuel region 20, and the distance from the lid 6 is such that the storage container 4 is at a height approximately at the center of the core fuel region 20. It is provided at a position approximately equal to 1/2 of the height of the core fuel region 20.
この後備炉停止棒は、別の場所において製作する。その
方法は、まず停止棒ラッパ管8内を真空状態にして隔壁
IOの流通孔12を通して図示しない不活性ガス供給用
のホースを挿入し、上から冷却材である液体す) IJ
ウムを入れると、内筒1内も液体ナトリウムで満たされ
る。この状態で不活性ガスを供給するとガスは内筒1内
の上部に満たされる。そしてホースを抜きとっておくと
、最終的にはす) IJウムは冷えて固化する。このナ
トリウムが固化した状態の炉停止棒を炉に装荷するとす
) IJウムが溶けて作動する状態となる。This back-up reactor shutdown rod will be manufactured at a separate location. The method is to first create a vacuum inside the stop rod trumpet tube 8, insert an inert gas supply hose (not shown) through the flow hole 12 of the partition wall IO, and then pour the coolant liquid from above.
When sodium is added, the inside of the inner cylinder 1 is also filled with liquid sodium. When inert gas is supplied in this state, the upper part of the inner cylinder 1 is filled with the gas. Then, if you remove the hose, the IJum will cool and solidify. If the furnace is loaded with a reactor stop rod containing solidified sodium, the IJium will melt and become operational.
運転状態では中性子吸収体3は炉心燃料領域20の外側
に位置し、炉停止棒ラッパ管8の周囲の炉心燃料集合体
15からの中性子を減速、吸収することなく原子炉の正
常運転を行うことができる。In the operating state, the neutron absorber 3 is located outside the core fuel region 20, and allows the reactor to operate normally without decelerating or absorbing neutrons from the core fuel assembly 15 around the reactor shutdown rod trumpet tube 8. I can do it.
冷却材13が異常温度、例えば600℃に達すると、不
活性ガスの膨張による浮力で内筒1が炉停止環ラッパ管
8内を上昇するように不活性ガス7の量を調整しておけ
ば正常運転時は炉停止棒ラッパ管8の上部プレナム14
の温度が正常温度、例えば550℃に保たれている場合
は、図に示すように収納容器3すなわち中性子吸収体3
は炉心燃料領域20の下方にある。しかし、第1次主循
環ポンプ等の異常で冷却材の流量喪失が生じた場合、炉
心出口の冷却材の温度が異常に上昇し、炉停止棒うンパ
管8の周囲の炉心燃料集合体15からの熱伝達により、
内筒1内の不活性ガス7の温度が上昇して膨張する。そ
の結果、不活性ガス?空間の下にある冷却材13は下方
に圧力を受けて内筒lの下部から外に出て炉停止棒うン
パ管8内を上昇し、流通孔12から上部プレナム14内
に出てし)<。そのため内筒1は軽<iヨって収納室9
内を上昇する。このとき、内筒l下部に取付けられた収
納容器4内の中性子吸収体3は炉心燃料領域20に移動
し、中性子を吸収して異常温度上昇を抑制し、原子炉を
停止させる。この場合、内筒の重量に対するナトリウム
の浮力、ボロンの重量、中空支柱の重量及び浮力等を無
視した概略計算では、内筒の厚み約0.05cm、密度
10g/Crlとすると、内筒の重量は約3kgとなり
、この内筒を浮上させるのに必要なガス柱の高さは約4
5cmである。また、内筒1は支柱2で底板11を支え
ることなく下部に冷却材13の流通孔を1個または複数
個有する長尺の円筒で、直接底板11に置いてもよく、
多角形の形状であってもよい。本緊急炉停止機構は再使
用可能なこと言うまでもない。If the amount of inert gas 7 is adjusted so that when the coolant 13 reaches an abnormal temperature, for example, 600°C, the inner cylinder 1 will rise inside the reactor shutdown ring wrapper tube 8 due to the buoyancy caused by the expansion of the inert gas. During normal operation, the upper plenum 14 of the reactor stop rod trumpet tube 8
When the temperature of the storage container 3, that is, the neutron absorber 3
is below the core fuel region 20. However, if a loss of coolant flow occurs due to an abnormality in the primary main circulation pump, etc., the temperature of the coolant at the core outlet will rise abnormally, causing the core fuel assembly 15 around the reactor shutdown rod pumper pipe 8 to Due to heat transfer from
The temperature of the inert gas 7 in the inner cylinder 1 rises and expands. As a result, inert gas? The coolant 13 under the space is subjected to downward pressure and comes out from the lower part of the inner cylinder l, rises inside the reactor shutdown rod damper pipe 8, and comes out from the circulation hole 12 into the upper plenum 14.) <. Therefore, the inner cylinder 1 is light and has a storage compartment 9.
rise within. At this time, the neutron absorber 3 in the storage container 4 attached to the lower part of the inner cylinder l moves to the core fuel region 20, absorbs neutrons, suppresses abnormal temperature rise, and shuts down the reactor. In this case, a rough calculation that ignores the buoyancy of sodium, the weight of boron, the weight of the hollow support, and the buoyancy with respect to the weight of the inner cylinder shows that if the thickness of the inner cylinder is approximately 0.05 cm and the density is 10 g/Crl, then the weight of the inner cylinder is is approximately 3 kg, and the height of the gas column required to levitate this inner cylinder is approximately 4 kg.
It is 5cm. In addition, the inner cylinder 1 may be a long cylinder having one or more circulation holes for the coolant 13 at the bottom without supporting the bottom plate 11 with the struts 2, and may be placed directly on the bottom plate 11.
It may also have a polygonal shape. Needless to say, this emergency reactor shutdown mechanism is reusable.
以上のように本発明によれば、異常温度発生時、炉心出
口の冷却材の温度上昇による不活性ガスの熱膨張という
物理現象によって原子炉の緊急停止が行われるが、炉心
出口の温度変化のみならず、上部プレナム内の圧力変化
、例えば−次主循環ボンプの作動時は高圧で、停止時は
低圧となるような一次主循環ポンプ故障を含む一次主循
環系の破損による原子炉内の圧力低下によっても即時応
答する効果を有している。As described above, according to the present invention, when an abnormal temperature occurs, an emergency shutdown of the reactor is performed due to the physical phenomenon of thermal expansion of the inert gas due to the temperature rise of the coolant at the core exit, but only the temperature change at the core exit pressure in the reactor due to damage to the primary main circulation system, including failure of the primary main circulation pump, such as pressure changes in the upper plenum, such as high pressure when the main circulation pump is operating and low pressure when it is stopped. It has the effect of providing an immediate response even when the temperature decreases.
また、自己検出作動型であるので、計測制御機器の異常
や人為的な原因による誤動作を生ずることなく、安全性
、信頼性を向上させることができ、常時、中性子吸収体
を炉心部に装荷しているので、耐震性を向上させるとか
できる。In addition, since it is a self-detection type, it can improve safety and reliability without causing malfunctions due to abnormalities in measurement and control equipment or human causes. Therefore, it is possible to improve earthquake resistance.
第1図は本発明による緊急炉心停止機構の一実施例を示
す側面図、第2図および第3図はそれぞれ第1図のAA
’断面およびBB’断面を示す図、第4図は従来の後備
炉停止棒による緊急炉心停止機構の原子炉炉心部の説明
図である。
1・・・内筒、2・・・支柱、3・・・中性子吸収体、
4・・・収納容器、5・・・支持棒、7・・・不活性ガ
ス、8・・・炉停止棒ラッパ管、9・・・収納室、13
・・・冷却材、15・・・炉心燃料集合体、20・・・
炉心燃料領域、21・・・後備炉停止棒。FIG. 1 is a side view showing one embodiment of the emergency core shutdown mechanism according to the present invention, and FIGS. 2 and 3 are AA of FIG. 1, respectively.
FIG. 4 is an explanatory diagram of a nuclear reactor core part of an emergency core shutdown mechanism using a conventional back-up reactor shutdown rod. 1... Inner cylinder, 2... Support column, 3... Neutron absorber,
4...Storage container, 5...Support rod, 7...Inert gas, 8...Furnace stop rod trumpet tube, 9...Storage chamber, 13
...Coolant, 15...Core fuel assembly, 20...
Core fuel area, 21...Backup reactor shutdown rod.
Claims (4)
止棒と、該収納室内に配置され、中性子吸収体を保持す
る不活性ガスを収納した下端開放の中性子吸収体保持手
段とを備え、異常温度上昇による不活性ガスの膨張によ
り中性子吸収体保持手段内の冷却材を流出させ、中性子
吸収体保持手段を浮上させて中性子吸収体を炉心燃料領
域へ移動させることを特徴とする緊急炉心停止機構。(1) A reactor shutdown rod that has a storage chamber at its lower end into which coolant can flow, and a neutron absorber holding means that is open at the lower end and contains an inert gas that holds the neutron absorber and is placed inside the storage chamber. In case of an emergency, the coolant inside the neutron absorber holding means is caused to flow out due to the expansion of inert gas due to an abnormal temperature rise, the neutron absorber holding means is levitated, and the neutron absorber is moved to the core fuel area. Core shutdown mechanism.
からなる請求項1記載の緊急炉心停止機構。(2) The emergency core shutdown mechanism according to claim 1, wherein the neutron absorber holding means comprises a cylindrical body with an open bottom end.
の底板上に支持されていることを特徴とする請求項1記
載の緊急炉心停止機構。(3) The emergency core shutdown mechanism according to claim 1, wherein the neutron absorber holding means is supported by a support on the bottom plate of the stop rod.
通孔を有することを特徴とする請求項1記載の緊急炉心
停止機構。(4) The emergency core shutdown mechanism according to claim 1, wherein the upper partition wall forming the storage chamber has coolant flow holes.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2040835A JPH07113674B2 (en) | 1990-02-21 | 1990-02-21 | Emergency core shutdown mechanism |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2040835A JPH07113674B2 (en) | 1990-02-21 | 1990-02-21 | Emergency core shutdown mechanism |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH03243891A true JPH03243891A (en) | 1991-10-30 |
JPH07113674B2 JPH07113674B2 (en) | 1995-12-06 |
Family
ID=12591690
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2040835A Expired - Fee Related JPH07113674B2 (en) | 1990-02-21 | 1990-02-21 | Emergency core shutdown mechanism |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH07113674B2 (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2709858A1 (en) * | 1993-09-08 | 1995-03-17 | Toshiba Kk | Fast neutron reactor core with gas-sealed assemblies |
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 |
JP2021135248A (en) * | 2020-02-28 | 2021-09-13 | 日立Geニュークリア・エナジー株式会社 | Fast reactor core, and operation method of fast reactor |
-
1990
- 1990-02-21 JP JP2040835A patent/JPH07113674B2/en not_active Expired - Fee Related
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2709858A1 (en) * | 1993-09-08 | 1995-03-17 | Toshiba Kk | Fast neutron reactor core with gas-sealed assemblies |
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 |
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 |
JP2021135248A (en) * | 2020-02-28 | 2021-09-13 | 日立Geニュークリア・エナジー株式会社 | Fast reactor core, and operation method of fast reactor |
US11854709B2 (en) | 2020-02-28 | 2023-12-26 | Hitachi-Ge Nuclear Energy, Ltd. | Fast reactor with primary and backup control rods |
Also Published As
Publication number | Publication date |
---|---|
JPH07113674B2 (en) | 1995-12-06 |
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