JPH0559398B2 - - Google Patents
Info
- Publication number
- JPH0559398B2 JPH0559398B2 JP63119014A JP11901488A JPH0559398B2 JP H0559398 B2 JPH0559398 B2 JP H0559398B2 JP 63119014 A JP63119014 A JP 63119014A JP 11901488 A JP11901488 A JP 11901488A JP H0559398 B2 JPH0559398 B2 JP H0559398B2
- Authority
- JP
- Japan
- Prior art keywords
- electromagnet
- control rod
- reactor
- joints
- holding mechanism
- 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 - Lifetime
Links
- 230000007246 mechanism Effects 0.000 claims description 19
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical group [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 11
- 238000005452 bending Methods 0.000 description 11
- 239000002826 coolant Substances 0.000 description 7
- 239000012530 fluid Substances 0.000 description 5
- 239000000696 magnetic material Substances 0.000 description 5
- 230000007257 malfunction Effects 0.000 description 5
- 238000010586 diagram Methods 0.000 description 3
- 230000002159 abnormal effect Effects 0.000 description 2
- 230000005856 abnormality Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 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 description 1
- 239000006096 absorbing agent Substances 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 230000005389 magnetism Effects 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 238000001179 sorption measurement Methods 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Manipulator (AREA)
Description
【発明の詳細な説明】
[産業上の利用分野]
本発明は正常時は制御棒を電磁石により吊り下
げ保持し、非常発生時に原子炉を緊急停止させる
ため切り離して制御棒を炉心へ挿入する機構に関
し、更に詳しくは、電磁石の上方と下方とにそれ
ぞれ連結角度を自由に可変できる関節部を設け
て、冷却材の流体振動に伴う制御棒の保持−切り
離しの誤動作を防止できるようにした原子炉の制
御棒保持機構に関するものである。[Detailed Description of the Invention] [Industrial Application Field] The present invention is a mechanism in which control rods are suspended and held by electromagnets during normal operation, and are separated and inserted into the reactor core in order to stop the reactor in an emergency. In more detail, a nuclear reactor is provided with joints that can freely change the connection angle above and below the electromagnets to prevent malfunctions in holding and separating the control rods due to fluid vibrations of the coolant. This relates to the control rod holding mechanism.
[従来の技術]
一般に高速炉等では炉停止の信頼性を高めるた
め異常時等の制御棒を炉心に挿入する機構を備え
ている。この機構の信頼性を高めるために、外部
からの操作や信号に依存せずに原子炉を安全に停
止させることができるように自己作動型電磁石を
組み込んだ構成が提案されている。[Prior Art] In general, fast reactors and the like are equipped with a mechanism for inserting control rods into the reactor core in the event of an abnormality, etc., in order to increase the reliability of reactor shutdown. In order to increase the reliability of this mechanism, a configuration has been proposed that incorporates self-actuating electromagnets so that the reactor can be safely shut down without relying on external operations or signals.
この種の制御棒保持機構としては例えば第2図
に示すような構成がある。中性子吸収体を有する
制御棒10は炉心部の案内管12内に位置し炉内
冷却材14(高速増殖炉では通常液体ナトリウ
ム)中で保持される。制御棒保持機構は駆動軸1
6と、その下端に位置する自己作動型電磁石18
等を備え、該電磁石18の磁気的吸引力によつて
前記制御棒10を保持する。 An example of this type of control rod holding mechanism is the structure shown in FIG. A control rod 10 having a neutron absorber is located in a guide tube 12 in the reactor core and is held in a reactor coolant 14 (usually liquid sodium in a fast breeder reactor). The control rod holding mechanism is the drive shaft 1
6 and a self-actuating electromagnet 18 located at its lower end.
etc., and the control rod 10 is held by the magnetic attraction force of the electromagnet 18.
自己作動型電磁石18は、第1及び第2の鉄芯
20,22を組み合わせた二分割構造の鉄芯とコ
イル24とを具備し、磁気回路の一部に感温磁性
材26を組み込んだ構成である。なお符号28は
非磁性連結部材を示す。 The self-actuating electromagnet 18 has a two-part iron core, which is a combination of first and second iron cores 20 and 22, and a coil 24, and has a temperature-sensitive magnetic material 26 incorporated in a part of the magnetic circuit. It is. Note that the reference numeral 28 indicates a non-magnetic connecting member.
自己作動型電磁石18は前述したように炉内冷
却材14中に置かれている。従つて炉内に何らか
の異常が生じて周囲温度が上昇すると、感温磁性
材26はその異常温度に感応して磁性を失うため
鉄芯20,22同士の吸着部での磁気的吸引力が
低下し、切り離された制御棒10は自重により落
下し原子炉を停止させる。 A self-actuating electromagnet 18 is placed within the reactor coolant 14 as previously described. Therefore, if some abnormality occurs in the furnace and the ambient temperature rises, the temperature-sensitive magnetic material 26 will respond to the abnormal temperature and lose its magnetism, resulting in a decrease in the magnetic attraction force at the adhesion part between the iron cores 20 and 22. However, the separated control rod 10 falls due to its own weight, stopping the reactor.
[発明が解決しようとする課題]
上記のように制御棒10は、通常、炉内冷却材
14の中に吊り下げられており、冷却材流動に伴
う振動を受けて揺れが生じる。このため電磁石1
8を構成している分割構造の鉄芯20,22の吸
着部には曲げ応力が発生する。制御棒10や電磁
石18を固定している駆動軸16は長いため、そ
の曲げモーメントはかなり大きくなり、前記曲げ
応力によつて吸着面の一端が口を開くことにな
る。これは磁気的吸引力の急激な低下をもたら
し、定常運転中に制御棒10が落下するという誤
動作が生じることになる。[Problems to be Solved by the Invention] As described above, the control rod 10 is normally suspended in the in-core coolant 14, and shakes due to vibrations caused by the flow of the coolant. Therefore, electromagnet 1
Bending stress is generated in the suction portions of the iron cores 20 and 22 of the divided structure forming the structure 8. Since the drive shaft 16 to which the control rod 10 and the electromagnet 18 are fixed is long, its bending moment becomes quite large, and one end of the suction surface opens due to the bending stress. This causes a sudden decrease in the magnetic attraction force, resulting in a malfunction in which the control rod 10 falls during steady operation.
特に感温磁性材26を組み込んだ自己作動型電
磁石では、温度異常時の製御棒切り離し動作を確
実にするため定常運転時の磁気的吸引力をあまり
大きく設定きないので流体振動による誤動作の危
険性は高い。 In particular, with a self-actuating electromagnet that incorporates a temperature-sensitive magnetic material 26, the magnetic attraction force during steady operation cannot be set too large in order to ensure the operation of separating the rolling rod in the event of an abnormal temperature, so there is a risk of malfunction due to fluid vibration. The quality is high.
本発明の目的は、上記のような従来技術の欠点
を解消し、流体振動により電磁石の吸着面に発生
する曲げモーメントを減少させることができ、そ
のため定常運転中に制御棒が切り離される誤動作
を防止でき、また定常運転中の電磁石による磁気
的吸引力を低く設定することができ、それらによ
つて自己作動型炉停止機構の信頼性を大幅に向上
させることができるような制御棒保持機構を提供
することにある。 The purpose of the present invention is to eliminate the drawbacks of the prior art as described above, and to reduce the bending moment generated on the attraction surface of the electromagnet due to fluid vibration, thereby preventing malfunctions in which control rods are separated during steady operation. In addition, the magnetic attraction force generated by the electromagnet during steady operation can be set to a low level, thereby significantly improving the reliability of the self-actuated reactor shutdown mechanism. It's about doing.
[課題を解決するための手段]
上記の目的を達成できる本発明は、駆動軸の下
端に二分割構造の鉄芯のコイルとを組み合わせた
電磁石を設け、該電磁石により制御棒の吊り下げ
保持−切り離しを行う機構において、電磁石の上
方と下方とにそれぞれ連結角度を可変自在の関節
部を設けた原子炉の制御棒保持機構である。[Means for Solving the Problems] The present invention, which can achieve the above objects, provides an electromagnet in combination with a two-part iron core coil at the lower end of the drive shaft, and uses the electromagnet to suspend and hold the control rod. This disconnection mechanism is a control rod holding mechanism for a nuclear reactor that has joints above and below the electromagnet that can change the connection angle.
ここで連結部の角度を可変自在の関節部として
は、例えばボール・ソケツト継手が好適である。 For example, a ball-and-socket joint is suitable as the joint part that can freely change the angle of the connecting part.
[作用]
電磁石の上方及び下方にそれぞれボール・ソケ
ツト継手のような関節部を設けると、それらによ
り連結された部材は相互の連結角度を自由に可変
できるようになる。つまり電磁石は上方の関節部
を介して駆動軸に吊り下げられ、また制御棒は下
方の関節部を介して電磁石に吊り下げられる構造
になるから、制御棒及び電磁石に流体振動による
揺れが生じると、それらの関節部で曲がるため電
磁石の分割された鉄芯の吸着面に発生する曲げ応
力は極めて小さくなる。[Operation] When joints such as ball-and-socket joints are provided above and below the electromagnet, the mutual connection angles of the members connected by these joints can be freely varied. In other words, the electromagnet is suspended from the drive shaft via the upper joint, and the control rod is suspended from the electromagnet via the lower joint, so if the control rod and electromagnet are shaken by fluid vibration, , because it bends at those joints, the bending stress generated on the adsorption surface of the electromagnet's divided iron core becomes extremely small.
このため定常運転中に電磁石が切り離される危
険性がなくなると共に、電磁石に発生させる磁気
的吸引力は従来技術に比べて少なくて済む。 Therefore, there is no risk of the electromagnet being disconnected during steady operation, and the magnetic attraction force generated in the electromagnet can be smaller than in the prior art.
[実施例]
第1図は本発明に係る制御棒保持機構の一実施
例を示す説明図である。駆動軸16の下方に電磁
石18が位置し、それに制御棒10が吊り下げら
れている。制御棒10は案内管12内に挿入され
ており、炉内冷却材14の中に位置している。こ
のような基本構成は前記第2図に示す従来技術と
同様である。[Embodiment] FIG. 1 is an explanatory diagram showing an embodiment of a control rod holding mechanism according to the present invention. An electromagnet 18 is located below the drive shaft 16, and a control rod 10 is suspended from it. The control rod 10 is inserted into the guide tube 12 and located within the reactor coolant 14 . This basic configuration is similar to the prior art shown in FIG. 2 above.
使用する電磁石18も基本的には従来技術と同
様であつてよい。即ち、第1及び第2の鉄芯2
0,22を組み合わせた二分割構造の鉄芯とコイ
ル24とを具備し、磁気回路の一部に感温磁性材
26が組み込まれている構成である。符号28は
非磁性連結部材を示す。 The electromagnet 18 used may also be basically the same as in the prior art. That is, the first and second iron cores 2
It has a two-part iron core and a coil 24, and a temperature-sensitive magnetic material 26 is incorporated in a part of the magnetic circuit. Reference numeral 28 indicates a non-magnetic connecting member.
ここで本発明が従来技術と顕著に相違する点
は、駆動軸16と電磁石18との間、及び電磁石
18と制御棒10との間の結合構造である。 Here, the present invention is significantly different from the prior art in the coupling structure between the drive shaft 16 and the electromagnet 18 and between the electromagnet 18 and the control rod 10.
第1図からも分かるように本発明ではボール・
ソケツト継手のような関節部30,32が用いら
れ、それによつて相互の連結角度を自由に可変で
きるような機構になつている。つまり電磁石18
は上方の関節部30によつて駆動軸16は吊り下
げられており、また制御棒10は下方の関節部3
2によつて電磁石18に吊り下げられている。 As can be seen from Fig. 1, in the present invention, the ball
Joints 30 and 32 such as socket joints are used to provide a mechanism that allows the mutual connection angle to be freely varied. In other words, electromagnet 18
The drive shaft 16 is suspended by the upper joint 30, and the control rod 10 is suspended by the lower joint 30.
2 to the electromagnet 18.
流体振動によつて制御棒10及び電磁石18に
揺れが生じると、上方及び下方の関節部30,3
2を中心に曲がり、電磁石18の鉄芯20,22
間の吸着面に発生する曲げ応力は極めて小さくな
る。このため定常運転中に曲げ応力によつて吸着
面で切り離される虞れはない。また吸着面に発生
する曲げ応力が小さいため、磁気的吸引力を従来
よりも小さく設定することが可能となる。 When the control rod 10 and electromagnet 18 shake due to fluid vibration, the upper and lower joints 30, 3
2, the iron cores 20, 22 of the electromagnet 18
The bending stress generated on the suction surface between the two is extremely small. Therefore, there is no risk of separation at the suction surface due to bending stress during steady operation. Furthermore, since the bending stress generated on the attraction surface is small, it is possible to set the magnetic attraction force to be smaller than before.
実際に同一の電磁石を用いて制御棒を吸着保持
させた後、制御棒に揺れを与えて落下する揺れ大
きさを比較すると、本発明のように関節部を有す
る場合ははるかに大きな揺れ幅でも落下しないこ
とが認められた。 Comparing the magnitude of the shaking when the control rod is actually attracted and held using the same electromagnet and then shaken, it is found that when the control rod has joints as in the present invention, the shaking width is much larger. It was confirmed that it did not fall.
なお上記のような構成において発生する曲げモ
ーメントはおよそ上方の関節部30と下方の関節
部32との長さに比例するから、それら二つの関
節部30,32間の距離をできるだけ小さく設定
することが望ましい。 Note that since the bending moment generated in the above configuration is approximately proportional to the length of the upper joint 30 and the lower joint 32, the distance between these two joints 30 and 32 should be set as small as possible. is desirable.
関節部の構造は特に限定されるものではない。
第1図に示したようなボール・ソケツト継手が望
ましいが、連結角度を自由に可変できるような構
造であれば他の機構であつてもよい。 The structure of the joint is not particularly limited.
Although a ball and socket joint as shown in FIG. 1 is preferable, other mechanisms may be used as long as the connection angle can be freely varied.
[発明の効果]
本発明は上記のように電磁石の上方と下方とに
それぞれ連結角度を可変自在の関節部を設けた原
子炉の制御棒保持機構であるから、冷却材の流体
振動によつて制御棒及び電磁石に曲げモーメント
が加わると、それらは関節部によつて鉛直軸の回
りに揺れ、そのため吸着面に発生する曲げ応力を
小さくでき、従つて定常運転中に電磁石が切り離
されて制御棒が落下するといつた誤動作の発生を
防止できる効果がある。[Effects of the Invention] As described above, the present invention is a control rod holding mechanism for a nuclear reactor in which joints are provided above and below the electromagnet with variable connection angles. When a bending moment is applied to the control rod and electromagnet, the joints cause them to swing around the vertical axis, which reduces the bending stress generated on the attraction surface. Therefore, during steady operation, the electromagnet is disconnected and the control rod This has the effect of preventing malfunctions that may occur if the device falls.
また上記の理由で定常運転中の電磁石による磁
気的吸引力を低く設定できるため、炉内温度が異
常上昇した時の制御棒切り離しが一層容易にな
り、自己作動型炉停止機構の信頼性は大幅に向上
する。 Additionally, for the above reasons, the magnetic attraction force generated by the electromagnet during steady operation can be set low, making it easier to disconnect the control rods when the temperature inside the reactor rises abnormally, greatly improving the reliability of the self-actuated reactor shutdown mechanism. improve.
第1図は本発明に係る制御棒保持機構の一実施
例を示す説明図、第2図は従来技術の一例を示す
説明図である。
10……制御棒、12……案内管、14……炉
内冷却材、16……駆動軸、18……電磁石、2
0,22……鉄芯、24……コイル、26……感
温磁性材、30,32……関節部。
FIG. 1 is an explanatory diagram showing an embodiment of a control rod holding mechanism according to the present invention, and FIG. 2 is an explanatory diagram showing an example of a conventional technique. 10... Control rod, 12... Guide tube, 14... In-reactor coolant, 16... Drive shaft, 18... Electromagnet, 2
0, 22... Iron core, 24... Coil, 26... Temperature-sensitive magnetic material, 30, 32... Joint part.
Claims (1)
を組み合わせた電磁石を設け、該電磁石により制
御棒の吊り下げ保持−切り離しを行う機構におい
て、電磁石の上方と下方とにそれぞれ連結角度を
可変自在の関節部を設けたことを特徴とする原子
炉の制御棒保持機構。 2 関節部がボール・ソケツト継手である請求項
1記載の制御棒保持機構。[Claims] 1. In a mechanism in which an electromagnet consisting of a two-split iron core and a coil is provided at the lower end of the drive shaft, and the electromagnet suspends and holds and disconnects the control rod, the upper and lower parts of the electromagnet are connected to each other. A control rod holding mechanism for a nuclear reactor, characterized in that a control rod holding mechanism for a nuclear reactor is provided with joints whose connection angles can be freely changed. 2. The control rod holding mechanism according to claim 1, wherein the joint is a ball and socket joint.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63119014A JPH01288798A (en) | 1988-05-16 | 1988-05-16 | Holding mechanism for nuclear reactor control rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63119014A JPH01288798A (en) | 1988-05-16 | 1988-05-16 | Holding mechanism for nuclear reactor control rod |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01288798A JPH01288798A (en) | 1989-11-21 |
| JPH0559398B2 true JPH0559398B2 (en) | 1993-08-30 |
Family
ID=14750852
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63119014A Granted JPH01288798A (en) | 1988-05-16 | 1988-05-16 | Holding mechanism for nuclear reactor control rod |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01288798A (en) |
-
1988
- 1988-05-16 JP JP63119014A patent/JPH01288798A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPH01288798A (en) | 1989-11-21 |
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