JPS5890196A - Reactor core reactivity control device - Google Patents
Reactor core reactivity control deviceInfo
- Publication number
- JPS5890196A JPS5890196A JP56188436A JP18843681A JPS5890196A JP S5890196 A JPS5890196 A JP S5890196A JP 56188436 A JP56188436 A JP 56188436A JP 18843681 A JP18843681 A JP 18843681A JP S5890196 A JPS5890196 A JP S5890196A
- Authority
- JP
- Japan
- Prior art keywords
- core
- rod
- control
- control rod
- reactor
- 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
- Steering Control In Accordance With Driving Conditions (AREA)
- Electromagnets (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
本発明は軽水形原子炉の炉心反応度制御を行なう炉心反
応度制御装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a core reactivity control device for controlling core reactivity of a light water nuclear reactor.
一般（＝、軽水形原子炉においては、炉心の反応度を制
御するために、制御棒とこれを駆動する駆動機構とから
なる炉心反応度制御装置が配設されている。In a general (=, light water nuclear reactor), a core reactivity control device consisting of a control rod and a drive mechanism that drives the control rod is provided in order to control the reactivity of the reactor core.
従来の沸騰水形原子炉においては、炉心反応度制御をつ
かさどる制御棒の炉心への挿入引抜き操作は、原子炉下
部；＝設置された駆動機構により行なわれており、制御
棒を炉心から引抜く場合には、制御棒は下方向に駆動さ
れ、下方向のストローク限界まで駆動されると全引抜き
状態とされる。In conventional boiling water reactors, the operation of inserting and withdrawing control rods, which control core reactivity, into the reactor core is performed by a drive mechanism installed at the bottom of the reactor; In this case, the control rod is driven downward, and when it is driven to the limit of its downward stroke, it is fully withdrawn.
逆に制御棒を炉心に挿入する場合（−は制御棒は上方向
に駆動され上方向のストローク限界まで駆動されると全
挿入状態とされる。Conversely, when a control rod is inserted into the reactor core (-, the control rod is driven upward and is fully inserted when it is driven to the upper stroke limit.
したがって、このような原子炉においては、核反応停車
のため制御棒を緊急挿入する場合には、制御棒は重力方
向と反対の上方向に挿入駆動されることになる。Therefore, in such a nuclear reactor, when a control rod is inserted in an emergency to stop a nuclear reaction, the control rod is inserted and driven in an upward direction opposite to the direction of gravity.
また、制御棒の炉心への挿入状態（＝おいて何らかの理
由で制御棒駆動機構が機能を喪失した場合、または制御
棒と駆動装置の連結部分が外れて、制御棒を炉心におい
たまま、駆動機構が全引抜き位置まで引抜かれた場合、
制御棒は炉心から下方向へ落下し、異常核反応をおこす
可能性がある。In addition, if the control rod drive mechanism loses its function for some reason when the control rod is inserted into the reactor core, or if the connection between the control rod and the drive device becomes disconnected, the control rod is inserted into the reactor core and the control rod is not driven. When the mechanism is withdrawn to the fully withdrawn position,
The control rods could fall downward from the core and cause an abnormal nuclear reaction.
そこで駆動機構を原子炉の上部に取付けることが考えら
れるが、この場合には、原子炉圧力容器の蓋を取付ける
段階で、制御棒と駆動機構の連結を確実に行なう必要が
あり、その確認方法が複雑で難しいという問題がある。Therefore, it is possible to install the drive mechanism at the top of the reactor, but in this case, it is necessary to ensure the connection between the control rods and the drive mechanism at the stage of attaching the reactor pressure vessel lid, and how to confirm this. The problem is that it is complex and difficult.
また、この場合には原子炉上部に設置した駆動機構と制
御棒とを連結するため制御棒の頂部（上部）に連結機構
が必要となり、また、燃料交換を上方から行うことにな
るので連結機構がじゃまになるという問題がある。In this case, a connecting mechanism is required at the top (upper part) of the control rod to connect the drive mechanism installed at the top of the reactor and the control rod, and since fuel exchange will be performed from above, the connecting mechanism is required. There is a problem that it gets in the way.
さらに、従来の沸騰水形原子炉では、制御棒は、炉心下
方から炉心内に挿入されることとなるため、制御棒の落
下事故に備え流体抵抗部組であるスピードリミッタ−が
配設されているが、このスピードリミッタ−は、制御棒
の馬区動時に大きな流体抵抗を生じるため、炉心反応度
制御装置が非常に大がかりなものになるという問題があ
った。Furthermore, in conventional boiling water reactors, control rods are inserted into the reactor core from below, so a speed limiter, which is a fluid resistance unit, is installed in case a control rod falls. However, this speed limiter creates a large fluid resistance when the control rods move, so there is a problem in that the core reactivity control device becomes very large-scale.
本発明は、かかる従来の事情に対処してなされたもので
、多数の矩形燃料集合体を基板目状に配置した炉心と、
この炉心上方と前記燃料集合体間を上下して前記炉心内
の反応度を制御する流体抵抗部材を有しない断面十字形
状をした制御棒と、この制御棒の下端に一端を接続し他
端を下方に延長させた駆動ロンドと、この駆動ロンドを
上下に駆動する前記炉心下方に配設された駆動機構とか
らなることを特徴とする炉心反応度制御装置を提供しよ
うとするものである。The present invention has been made in response to such conventional circumstances, and includes a reactor core in which a large number of rectangular fuel assemblies are arranged in a grid pattern,
A control rod having a cross-shaped cross section without a fluid resistance member that moves up and down between the upper part of the reactor core and the fuel assembly to control the reactivity in the reactor core, and one end of which is connected to the lower end of this control rod and the other end of which is connected to the lower end of this control rod. It is an object of the present invention to provide a core reactivity control device characterized by comprising a driving rod extending downward and a drive mechanism disposed below the core for driving the driving rod up and down.
以下、本発明の詳細を図面に示す一実施例について説明
する。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Hereinafter, details of the present invention will be described with reference to an embodiment shown in the drawings.
第１図において符号１は、沸騰水形原子炉の原子炉圧力
容器を示しており、この原子炉圧力容器１内には多数の
矩形燃料集合体を基板目状に配置した炉心２が配設され
ている。In FIG. 1, reference numeral 1 indicates a reactor pressure vessel of a boiling water reactor, and within this reactor pressure vessel 1 is a reactor core 2 in which a large number of rectangular fuel assemblies are arranged in a grid pattern. has been done.
原子炉圧力容器１の炉心２下方には、貫通孔３が穿設さ
れ、この貫通孔３には、駆動機構ハウジング４が挿入さ
れている。A through hole 3 is bored below the core 2 of the reactor pressure vessel 1, and a drive mechanism housing 4 is inserted into the through hole 3.
駆動機構ハウジング４の上端開口部５には、この駆動機
構ハウジング４内を摺動自在とされる駆動ロッド６が挿
入されており、駆動ロンド乙の上端は、制御棒７の下端
に形成される連結部８に接続されている。A drive rod 6 that is slidable within the drive mechanism housing 4 is inserted into the upper end opening 5 of the drive mechanism housing 4, and the upper end of the drive rod 2 is formed at the lower end of the control rod 7. It is connected to the connecting part 8.
すなわち、駆動ロッド６が駆動機構ハウジング４の上方
に位置するときには、制御棒７は炉心２上方に位置し、
下方に位置するときには、制御棒７は炉心２内に挿入さ
れる。That is, when the drive rod 6 is located above the drive mechanism housing 4, the control rod 7 is located above the reactor core 2,
When located in the lower position, the control rods 7 are inserted into the reactor core 2 .
第２図は、制御棒７の詳細を示すもので図において符号
９は、断面十字形状をしたブレードを示している。FIG. 2 shows details of the control rod 7, and in the figure, reference numeral 9 indicates a blade having a cross-shaped cross section.
このブレード９には、多数のチューブ冷却孔１０が穿設
されており、ブレード９の上端および下端には、つり上
げハンドル１１および連結部８がそれぞれ固設されてい
る。This blade 9 is provided with a large number of tube cooling holes 10, and a lifting handle 11 and a connecting portion 8 are fixedly provided at the upper and lower ends of the blade 9, respectively.
ブレード９の内部は中空状とされており、この中空部に
は、多数のｉｌｅ’イズンチューブ１２が挿入されてい
る。The inside of the blade 9 is hollow, and a large number of ile'in tubes 12 are inserted into this hollow part.
ポイズンチューブ１２内には、中性子吸収祠であるボロ
ン・カーバイトの粉末またはハフニューム合金が用いら
れている。Inside the poison tube 12, boron carbide powder or hafnium alloy, which serves as a neutron absorber, is used.
なおハフニューム合金は粉末にも、棒状にも加工できる
ので、粉末でしか使用できないボロン・カーバイトに比
較すると、応用範囲が広く、経済的に有利である。
・・
以上のように構成された炉心反応度制御装置では、炉心
反応度を高める場合には、駆動ロッド６は、駆動機構ハ
ウジング４に沿って上方に移動され、駆動ロッド６の上
端に連結された制御棒７は、炉心２上方に移動される。Furthermore, since hafnium alloy can be processed into powder or rod shape, it has a wider range of applications and is economically advantageous compared to boron carbide, which can only be used in powder form.
... In the core reactivity control device configured as above, when increasing the core reactivity, the drive rod 6 is moved upward along the drive mechanism housing 4 and connected to the upper end of the drive rod 6. The control rods 7 are moved above the reactor core 2.
逆に、炉心反応度を低下する場合には、駆動ロッド６は
、駆動機構ハウジング４に沿って下方に移動され駆動ロ
ッド６の上端に連結された制御棒７は、炉心２内に移動
される。Conversely, when reducing the core reactivity, the drive rod 6 is moved downward along the drive mechanism housing 4, and the control rod 7 connected to the upper end of the drive rod 6 is moved into the core 2. .
すなわち、以上のように構成された炉心反応度制御装置
では、例えば原子炉の核反応を緊急に停止する場合に、
制御棒７に対する下向きの駆動力として駆動ロッド６に
よる駆動力の他に自重による力をも利用できる。That is, in the core reactivity control device configured as described above, for example, when stopping a nuclear reaction in a nuclear reactor in an emergency,
As the downward driving force for the control rod 7, in addition to the driving force from the driving rod 6, the force due to its own weight can also be used.
また、原子炉の運転中に、万一制御棒７が落下したとし
ても炉心２に中性子吸収利が挿入されることになり、原
子炉の安全性は大巾に向上する。Further, even if the control rod 7 were to fall during operation of the nuclear reactor, a neutron absorber would be inserted into the reactor core 2, and the safety of the reactor would be greatly improved.
さらに、従来のように落下速度を抑制する必要がないの
で、制御棒７のスピードリミッタ−は不要となり、この
結果、駆動ロッド６を駆動する水の抵抗が小さくなり、
制御棒７の駆動力を従来より小さくすることができる。Furthermore, since there is no need to suppress the falling speed as in the past, a speed limiter for the control rod 7 is no longer necessary, and as a result, the resistance of the water that drives the drive rod 6 is reduced.
The driving force of the control rod 7 can be made smaller than before.
なお、第６図は、従来の制御棒を比較のために示すもの
で、図において符号１６は断面十字形状をしたブレード
を示しており、このブレード１６の下端には、流体抵抗
部材であるスピードリミッタ−１７が配設されている。FIG. 6 shows a conventional control rod for comparison. In the figure, reference numeral 16 indicates a blade having a cross-shaped cross section. At the lower end of this blade 16, there is a speed control rod which is a fluid resistance member. A limiter 17 is provided.
さらに、また駆動ロッド６を外した状態でも制御棒７の
中性子吸収材が炉心２に挿入された状態にあるので、例
えば、点検のため駆動ロッド６を外しても、燃料交換を
行なうことができる。Furthermore, even when the drive rod 6 is removed, the neutron absorbing material of the control rod 7 remains inserted into the reactor core 2, so even if the drive rod 6 is removed for inspection, for example, fuel can be replaced. .
第４図は、本発明の他の実施例を示すもので、図におい
て符号１６は制御棒な示している。FIG. 4 shows another embodiment of the present invention, in which reference numeral 16 indicates a control rod.
この制御棒１６は上半部１４は、すでに述べた制御棒７
のブレード９部と同様に構成されているが、この上半部
１４に続く下半部１５は中性子を吸収しにくいステンレ
ス鋼またはジルコニューム合金から構成されている。The upper half 14 of this control rod 16 is the control rod 7 mentioned above.
The lower half 15 following the upper half 14 is made of stainless steel or zirconium alloy, which is difficult to absorb neutrons.
なお、以上述べた部分以外は、第１図で示した炉心反応
度制御装置と同様に構成されているので、同一部分には
同一符号を付し説６明を省略する。It should be noted that the parts other than those described above are configured similarly to the core reactivity control device shown in FIG. 1, so the same parts are denoted by the same reference numerals and the description thereof will be omitted.
以上のように構成された炉心反応度制御装置では制御棒
１３の上半部１４を炉心２から上方向に全引抜状態にす
ると、炉心２の中には、制御棒１６の中性子を吸収しに
くい下半部１５が入ることとなり、いかなる場合も、駆
動ロッド６が炉心２内に挿入されることはない。In the core reactivity control device configured as described above, when the upper half 14 of the control rods 13 is fully withdrawn upward from the core 2, it becomes difficult for the neutrons of the control rods 16 to be absorbed into the core 2. The lower half 15 will enter, and the drive rod 6 will not be inserted into the core 2 under any circumstances.
したがって、駆動ロッド６径を炉心２寸法の制約を受け
ないで設計することができる。Therefore, the diameter of the drive rod 6 can be designed without being restricted by the dimensions of the core 2.
以上述べたように本発明によれば、従来の炉心反応度制
御装置のように制御棒の駆動装置の異常により炉心から
制御棒が抜は出ることはなくなり、逆に炉心に制御棒が
挿入されることになるので、より安全性の高い原子炉を
提供することができる。As described above, according to the present invention, unlike conventional core reactivity control devices, control rods are no longer removed from the reactor core due to an abnormality in the control rod drive device; on the contrary, control rods are not inserted into the reactor core. Therefore, a nuclear reactor with higher safety can be provided.
さらに、スピードリミッタ−は不要となり、この結果炉
心反応度制御装置を非常にコンパクトなものとすること
ができる。Furthermore, a speed limiter is not required, and as a result, the core reactivity control device can be made very compact.
第１図は、本発明の炉心反応度制御装置の一実施例を示
す縦断面図、第２図は第１図で示した制御棒の斜視図、
第６図は、従来の制御棒の斜視図、第４図は、本発明の
他の実施例を示す縦断面図である。
１ ・・・・・・ 原子炉圧力容器
２ ・・・・・・炉心
４ ・・・駆動機構ハウジング
６ ・・・・・・ 駆動ロッド
７ ・・・・・制御棒
（７３１７）代理人弁理士 則 近 憲 佑（ほか１名
）
−９−−６１
□
！
−８
一″ ７
８
と３
第２図
第４図
第３図FIG. 1 is a longitudinal sectional view showing an embodiment of the core reactivity control device of the present invention, FIG. 2 is a perspective view of the control rod shown in FIG. 1,
FIG. 6 is a perspective view of a conventional control rod, and FIG. 4 is a longitudinal sectional view showing another embodiment of the present invention. 1...Reactor pressure vessel 2...Reactor core 4...Drive mechanism housing 6...Drive rod 7...Control rod (7317) Agent patent attorney Noriyuki Chika (and 1 other person) -9--61 □! -8 1'' 7 8 and 3 Figure 2 Figure 4 Figure 3
Claims (1)
、この炉心上方と前記燃料集合体間を上下して前記炉心
内の反応度を制御する流体抵抗部材を有しない断面十字
形状をした制御棒と、この制御棒の下端に一端を接続し
他端を下方に延長させた駆動ロンドと、この駆動ロッド
を上下に駆動する前記炉心下方に配設された駆動機構と
からなることを特徴とする炉心反応度制御装置。1. A reactor core in which a large number of rectangular fuel assemblies are arranged in a grid pattern, and a cross-shaped cross-section without a fluid resistance member that moves up and down above the core and between the fuel assemblies to control the reactivity in the core. a control rod, a drive rod with one end connected to the lower end of the control rod and the other end extending downward, and a drive mechanism disposed below the core that drives the drive rod up and down. Characteristic core reactivity control device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56188436A JPS5890196A (en) | 1981-11-26 | 1981-11-26 | Reactor core reactivity control device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56188436A JPS5890196A (en) | 1981-11-26 | 1981-11-26 | Reactor core reactivity control device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5890196A true JPS5890196A (en) | 1983-05-28 |
Family
ID=16223639
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56188436A Pending JPS5890196A (en) | 1981-11-26 | 1981-11-26 | Reactor core reactivity control device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5890196A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5850078A (en) * | 1996-01-16 | 1998-12-15 | Symbol Technologies, Inc. | Simplified assembly and automatic testing of components in electro-optical systems for reading coded indicia |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5218592A (en) * | 1975-08-05 | 1977-02-12 | Nippon Kokan Kk <Nkk> | Control rod scram method |
-
1981
- 1981-11-26 JP JP56188436A patent/JPS5890196A/en active Pending
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5218592A (en) * | 1975-08-05 | 1977-02-12 | Nippon Kokan Kk <Nkk> | Control rod scram method |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5850078A (en) * | 1996-01-16 | 1998-12-15 | Symbol Technologies, Inc. | Simplified assembly and automatic testing of components in electro-optical systems for reading coded indicia |
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