JPH068872B2 - Control rod for nuclear reactor - Google Patents

Control rod for nuclear reactor

Info

Publication number
JPH068872B2
JPH068872B2 JP60019857A JP1985785A JPH068872B2 JP H068872 B2 JPH068872 B2 JP H068872B2 JP 60019857 A JP60019857 A JP 60019857A JP 1985785 A JP1985785 A JP 1985785A JP H068872 B2 JPH068872 B2 JP H068872B2
Authority
JP
Japan
Prior art keywords
neutron absorbing
control rod
wing
neutron
metal
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
Application number
JP60019857A
Other languages
Japanese (ja)
Other versions
JPS61180186A (en
Inventor
精 植田
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP60019857A priority Critical patent/JPH068872B2/en
Publication of JPS61180186A publication Critical patent/JPS61180186A/en
Publication of JPH068872B2 publication Critical patent/JPH068872B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Vibration Dampers (AREA)

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は沸騰水型原子炉等の原子炉の炉心部に挿入され
る原子炉用制御棒に関する。Description: TECHNICAL FIELD OF THE INVENTION The present invention relates to a control rod for a nuclear reactor inserted into a core portion of a nuclear reactor such as a boiling water reactor.

〔発明と技術的背景とその問題点〕[Invention, technical background and problems]

原子炉用制御棒には原子炉の出力分布および出力レベル
調整用の制御棒（以下、出力調整用制御棒という。）と
原子炉の安全停止用制御棒とがあり、これらは現在同じ
構成の制御棒が使用されている。しかし、原子炉の運転
法改良に関する研究が積極的に進められる中で最近は出
力調整用制御棒と安全停止用制御棒とが機能分担して使
用されるようになってきた。Control rods for reactors include control rods for adjusting the power distribution and output level of the reactor (hereinafter referred to as output control rods) and control rods for safe shutdown of the reactor. Control rods are used. However, as research on the improvement of the operation method of a nuclear reactor is actively promoted, recently, a control rod for power adjustment and a control rod for safe shutdown have been used by sharing functions.

一般に、沸騰水型原子炉では、制御棒は炉心下部から原
子炉内に挿入される。このうち、出力調整用制御棒は、
原子炉を高出力運転させる時でも多くの場合、炉心内に
挿入されており、多量の中性子照射を受ける。したがっ
て、炉出力調整用制御棒は、多量の中性子照射を受けて
も、核的特性があまり劣化しない、いわゆる長寿命型の
ものを使用することが好ましい。Generally, in a boiling water reactor, the control rods are inserted into the reactor from below the core. Of these, the control rod for output adjustment is
Even when the reactor is operated at high power, it is often inserted into the core and receives a large amount of neutron irradiation. Therefore, it is preferable to use a so-called long-life type control rod for adjusting the reactor power, which does not significantly deteriorate the nuclear characteristics even if a large amount of neutron irradiation is received.

一方、原子炉の安全停止用制御棒は、原子炉の高出力運
転時には炉心から引き抜かれているため、引抜状態でも
多量の中性子照射を受ける先端部を除き、殆ど中性子照
射を受けることがない。On the other hand, the control rods for safe shutdown of the nuclear reactor are extracted from the core during high-power operation of the nuclear reactor, so that they are hardly irradiated with neutrons except for the tip portion which receives a large amount of neutrons even in the extracted state.

また、炉出力調整用制御棒は原子炉の高出力運転時に炉
出力分布および出力レベルの調整用に使用されるもので
あるから、安全停止用制御棒よりもやや小さな反応度価
値のものでよく、安全停止用制御棒は原子炉を安全に停
止させ得るように、従来の制御棒より大きな反応度価値
を有することが必要である。反応度価値を増大させるた
めには、横断面十字状をなす制御棒のウィング内に中性
子吸収材である例えばＢ４Ｃ（ボロンカーバイド）を多
量に充填すればよい。Moreover, since the control rod for adjusting the reactor power is used for adjusting the reactor power distribution and power level during high power operation of the reactor, it may have a reactivity value slightly smaller than that of the control rod for safe shutdown. The control rod for safe shutdown needs to have greater reactivity value than the conventional control rod so that the reactor can be shut down safely. In order to increase the reactivity value, a large amount of neutron absorbing material such as B 4 C (boron carbide) may be filled in the wing of the control rod having a cross-shaped cross section.

ところで、従来の制御棒は、第９図（Ａ）および（Ｂ）
に示すように、十字状横断面を有するタイロッド１の各
突脚に、深いＵ字状断面のシース２を取付けてウィング
３を形成し、各ウィング３内に複数の中性子吸収棒４を
列状に装填することにより構成される。中性子吸収棒４
は被覆管５内にＢ４Ｃの中性子吸収材６を充填したもの
である。なお符号７はハンドル８を取付けた先端構造材
であり、この先端構造材７にはガイドローラ９が設けら
れている。By the way, the conventional control rod is shown in FIGS. 9 (A) and 9 (B).
As shown in FIG. 3, a wing 3 is formed by attaching a sheath 2 having a deep U-shaped cross section to each projecting leg of a tie rod 1 having a cross-shaped cross section, and a plurality of neutron absorbing rods 4 are arranged in rows in each wing 3. It is configured by loading into. Neutron absorbing rod 4
Indicates that the cladding tube 5 is filled with the B 4 C neutron absorbing material 6. Reference numeral 7 is a tip structural member to which a handle 8 is attached, and the tip structural member 7 is provided with a guide roller 9.

しかし、従来の制御棒は、第９図（Ａ）および（Ｂ）に
示すように構成されているため、シース２の寸法構造を
変更しない限り、ウィング３内に現在以上の中性子吸収
材６を充填することは困難である。しかも、１つの原子
炉内に寸法の異なる制御棒を使用することは炉構成上不
可能である。このため、第９図（Ａ）および（Ｂ）に示
す従来の制御棒においては、制御棒の寸法を変えないで
反応度価値の大きな制御棒を得ることが困難で、反応度
価値の大きな安全停止用制御棒を得ることができなかっ
た。However, since the conventional control rod is configured as shown in FIGS. 9 (A) and 9 (B), unless the dimensional structure of the sheath 2 is changed, the neutron absorbing material 6 higher than the present one is present in the wing 3. It is difficult to fill. Moreover, it is impossible to use control rods having different sizes in one reactor due to the reactor structure. Therefore, in the conventional control rod shown in FIGS. 9 (A) and 9 (B), it is difficult to obtain a control rod having a high reactivity value without changing the size of the control rod, and a safety having a high reactivity value is obtained. I couldn't get a stop control rod.

〔発明の目的〕[Object of the Invention]

本発明は上述した事情を考慮してなされたもので、充填
される中性子吸収材の形状、充填量、種類および組成比
を変えることによって、反応度価値が大きく、長寿命型
の安定停止用制御棒に適した原子炉用制御棒を提供する
ことを目的とする。The present invention has been made in consideration of the above-mentioned circumstances, and by changing the shape, the filling amount, the type, and the composition ratio of the filled neutron absorber, the reactivity value is large, and the long-life type stable stop control is performed. An object is to provide a control rod for a reactor suitable for the rod.

本発明の他の目的は反応度価値を大きくしても比較的軽
量で安価に製造することができる原子炉用制御棒を提供
することである。Another object of the present invention is to provide a control rod for a nuclear reactor which is relatively lightweight and can be manufactured inexpensively even if the reactivity value is increased.

〔発明の概要〕[Outline of Invention]

上述した目的を達成するために、本発明に係る原子炉用
制御棒は、先端構造材と下端構造材を結合したタイロッ
ドに、深いＵ字状断面のシースを取付けてウィングを構
成し、全体として十字状横断面を有する原子炉用制御棒
において、前記先端構造材に隣接するウィングの内部空
間に金属製長寿命型中性子吸収材を配設し、残りのウィ
ング内部空間に平板状の中性子吸収要素を複数個列状に
配列し、上記中性子吸収要素のうち、前記先端構造材側
の複数の中性子吸収要素の少なくとも側周を金属製周辺
中性子吸収材で取り囲み、この中性子吸収材をウィング
の内部空間内に収容したことを特徴とするものである。In order to achieve the above-mentioned object, a control rod for a reactor according to the present invention has a wing formed by attaching a deep U-shaped cross section sheath to a tie rod in which a tip structure material and a bottom structure material are combined. In a control rod for a reactor having a cross-shaped cross section, a metal long-life neutron absorber is arranged in the inner space of the wing adjacent to the tip structure material, and a flat neutron absorbing element is formed in the remaining wing inner space. Are arranged in a plurality of rows, among the neutron absorbing elements, at least the peripheral side of the plurality of neutron absorbing elements on the side of the tip structure material is surrounded by a peripheral neutron absorbing material made of metal, and the neutron absorbing material has an internal space of the wing. It is characterized by being housed inside.

〔発明の実施例〕Example of Invention

以下、本発明に係る原子炉用制御棒の好ましい実施例に
ついて添付図面を参照して説明する。A preferred embodiment of a reactor control rod according to the present invention will be described below with reference to the accompanying drawings.

第１図は本発明に係る原子炉用制御棒を示すもので、特
に安全停止用の制御棒に適する原子炉用制御棒である。
この原子炉制御棒はタイロッド１０を有し、このタイロ
ッド１０に先端構造材１１および図示しない下端構造材
が結合されて一体化される。先端構造材１１は原子炉用
制御棒の挿入を案内するガイドローラ１２を備えるとと
もに、操作用ハンドル１３が設けられる。FIG. 1 shows a control rod for a nuclear reactor according to the present invention, and is a control rod for a nuclear reactor which is particularly suitable as a control rod for safe shutdown.
This reactor control rod has a tie rod 10, and a tip structural member 11 and a lower end structural member (not shown) are joined and integrated with the tie rod 10. The tip structural member 11 is provided with a guide roller 12 for guiding the insertion of the reactor control rod, and is provided with an operating handle 13.

一方、タイロッド１０は十字状横断面を有し、その突脚
に深いＵ字状断面のシース１４が取付けられ、ウィング
１５が構成される。ウィング１５内には偏平な内部空間
が形成され、先端構造材１１に隣接するウィング１５の
内部空間には金属製長寿命型中性子吸収板１６が配設さ
れる。この中性子吸収板１６はハフニウム（Ｈｆ）ある
いはＨｆ−Ｚｒ合金で形成され、内部空間に係合する偏
平形状に構成される。例えばハフニウムは中性子吸収能
力が優れた金属材で、ボロンカーバイド（Ｂ４Ｃ）の３
〜６倍の寿命を有する。On the other hand, the tie rod 10 has a cross-shaped cross section, and a sheath 14 having a deep U-shaped cross section is attached to its projecting leg to form a wing 15. A flat inner space is formed in the wing 15, and a metal long-life neutron absorbing plate 16 is arranged in the inner space of the wing 15 adjacent to the tip structural member 11. The neutron absorbing plate 16 is made of hafnium (Hf) or Hf-Zr alloy and has a flat shape that engages with the internal space. For example, hafnium is a metal material with excellent neutron absorption capacity, and is a boron carbide (B 4 C) 3
~ 6 times longer lifespan.

長寿命型中性子吸収板１６は、制御棒を炉心から引き抜
いた時でも中性子に照射されるので、ハフニウムを主成
分とした寿命の大きな金属製の中性子吸収板が用いら
れ、その長さｌは５cm〜１５cm程度である。長寿命型中
性子吸収板１６の下端は外端側に向って下り傾斜してい
る。The long-lived neutron absorbing plate 16 is irradiated with neutrons even when the control rod is pulled out from the core, so a neutron absorbing plate made of hafnium as a main component and having a long life is used, and its length 1 is 5 cm. It is about 15 cm. The lower end of the long-life type neutron absorbing plate 16 is inclined downward toward the outer end side.

また、前記中性子吸収板１６に隣接するウィング１５の
内部空間には第１群および第２群の平板状の中性子吸収
要素１７，１８が複数個列状に密接して配列される。中
性子吸収要素１７，１８は第２図に示すように、ステン
レス製の平板状平缶１９内にボロンカーバイド（Ｂ
４Ｃ）の粉末や、ユーロッピア（Ｅｕ２Ｏ３）、ガドリ
ニア（Ｇｄ２Ｏ３）、サマリニア（Ｓｍ２Ｏ３）、ディ
スプロシァ（Ｄｙ２Ｏ３）等の希土類元素酸化物とハフ
ニア（ＨｆＯ２）との混合粉末あるいは粒状吸収材２０
を充填させたものである。In the inner space of the wing 15 adjacent to the neutron absorbing plate 16, a plurality of flat neutron absorbing elements 17 and 18 of the first group and the second group are closely arranged in a row. As shown in FIG. 2, the neutron absorbing elements 17 and 18 are made of stainless steel flat cans 19 and contain boron carbide (B).
4 C) powder, rare earth element oxides such as europia (Eu 2 O 3 ), gadolinia (Gd 2 O 3 ), sama linear (Sm 2 O 3 ), and disprosia (Dy 2 O 3 ), and hafnia (HfO 2 ). Mixed powder or granular absorbent material 20
It is filled with.

前述の各種中性子吸収材はそれぞれ単独もしくは複数の
希土類元素酸化物のみの混合物として使用することもで
きる。The above-mentioned various neutron absorbing materials can be used alone or as a mixture of plural rare earth element oxides.

中性子吸収要素１７は全体として偏平な平行四辺形状に
形成され、その上端面および下端面はウィング１５の外
側端に向って下り傾斜され、中性子吸収要素１７の平缶
１９内には溶接可能な金属スペーサ２１を分散的に配設
し、中性子吸収要素１７の対向する金属板間の間隔を一
定の範囲に保持している。The neutron absorbing element 17 is formed in a flat parallelogram shape as a whole, and the upper end surface and the lower end surface thereof are inclined downward toward the outer end of the wing 15, and a metal that can be welded into the flat can 19 of the neutron absorbing element 17. The spacers 21 are arranged dispersively, and the distance between the metal plates facing each other of the neutron absorbing element 17 is maintained within a certain range.

さらに、中性子吸収要素１７は内側の上端面側に吸収材
充填口２２が上方に突出して形成され、この充填口２２
から粉末あるいは粒状吸収材２０が充填され、その充填
後にプラグ２３で閉塞される。このとき、充填口２２は
プラグ２３で溶着されるが、この溶着時に熱が吸収材に
直接伝達されるのを防ぐため、充填口部には金属ウール
２４が介装される。しかして、中性子吸収要素１７に隣
接する上方の中性子吸収要素17には、吸収材充填口２２
に対応する係合段部２５が形成され、この係合段部によ
り複数の中性子吸収要素１７，１８の密接配列が可能に
なる。Further, the neutron absorbing element 17 is formed with an absorber filling port 22 protruding upward on the inner upper end surface side.
The powder or granular absorbent material 20 is filled from the above, and the plug 23 is closed after the filling. At this time, the filling port 22 is welded by the plug 23, but in order to prevent heat from being directly transferred to the absorbent material at the time of this welding, the metal wool 24 is interposed in the filling port portion. Therefore, in the upper neutron absorbing element 17 adjacent to the neutron absorbing element 17, the absorber filling port 22
Corresponding to the engagement stepped portion 25 is formed, and this engagement stepped portion enables a plurality of neutron absorbing elements 17 and 18 to be closely arranged.

中性子吸収要素１７，１８の平板状平缶１９内に例えば
粉末吸収材２０を充填させた場合、吸収材２０は原子炉
の運転に伴う各種振動により沈積が若干生じ、金属ウー
ム２４の下方に空隙が発生する。しかし、中性子吸収要
素１７，１８平缶１９の上端面および下端面は外側端面
に向って下り傾斜しているため、中性子吸収要素１７内
に発生する空隙はウィング１５の外側端まで発生するこ
とはない。反応度効果の観点からみると、ウィング１５
の内側端近傍はウィング外側端近傍に較べて制御棒の反
応度への寄与率が小さい。したがって、ウィング内側端
部に発生した空隙による制御棒反応との損失割合は外側
端部に発生した場合より小さい。すなわち、原子炉にお
ける反応度の損失を有効的に抑制することができる。When the flat plate-shaped cans 19 of the neutron absorbing elements 17 and 18 are filled with, for example, the powder absorbing material 20, the absorbing material 20 is slightly deposited due to various vibrations associated with the operation of the nuclear reactor, and a void is formed below the metal worm 24. Occurs. However, since the upper end surface and the lower end surface of the neutron absorbing elements 17 and 18 flat cans 19 are inclined downward toward the outer end surface, the void generated in the neutron absorbing element 17 does not occur up to the outer end of the wing 15. Absent. From the viewpoint of reactivity effect, wing 15
The contribution of the control rod to the reactivity is smaller near the inner edge of the wing than at the outer edge of the wing. Therefore, the loss ratio with the control rod reaction due to the void generated at the inner end of the wing is smaller than that at the outer end. That is, it is possible to effectively suppress the loss of the reactivity in the nuclear reactor.

また、原子炉用制御棒は先端構造材１１から制御棒全長
の約１／３程度の長さまでの間に収容される第１群の中
性子吸収要素１７の側周には、ハフニウムを主成分とす
る金属製周辺中性子吸収材２６で取り囲まれる。この中
性子吸収材２６は柱状に構成され、具体的には、第２図
に示すように、タイロッド１０側に配設された内側部中
性子吸収材２６ａとウィング１５の外側端側に配設され
た外側端中性子吸収材２６ｂと、各中性子吸収要素１
７，１７間に介装される吸収要素間中性子吸収材２６ｃ
とから構成される。Further, the control rod for a nuclear reactor contains hafnium as a main component on the side circumference of the neutron absorbing element 17 of the first group housed between the tip structural member 11 and the length of about 1/3 of the total length of the control rod. It is surrounded by a metallic peripheral neutron absorber 26. The neutron absorbing material 26 is formed in a columnar shape. Specifically, as shown in FIG. 2, the neutron absorbing material 26a is disposed on the inner side neutron absorbing material 26a disposed on the tie rod 10 side and on the outer end side of the wing 15. Outer edge neutron absorbing material 26b and each neutron absorbing element 1
Neutron absorbing material 26c between absorbing elements interposed between 7 and 17
Composed of and.

このように、第１群の中性子吸収要素１７の外周を取り
囲むように金属製周辺中性子吸収材２６を設けることに
より、第５図（Ａ）に示すように中性子吸収能力の有効
幅Ｗ１を拡張することができ、第５図（Ｂ）に示すよう
に金属製中性子吸収材を備えない中性子吸収要素１８の
ように中性子吸収能力の有効幅Ｗ２が狭いという問題が
解消される。In this way, by providing the metallic peripheral neutron absorbing material 26 so as to surround the outer periphery of the neutron absorbing element 17 of the first group, the effective width W 1 of the neutron absorbing capacity is expanded as shown in FIG. 5 (A). Therefore, the problem that the effective width W 2 of the neutron absorbing capacity is narrow unlike the neutron absorbing element 18 that does not include the metallic neutron absorbing material as shown in FIG. 5B is solved.

なお、先端構造材１１から制御棒の全長の約１／３以上
離れたウィング１５の内部空間に配設される第２群の中
性子吸収要素１８には、金属製周辺中性子吸収材２６は
配設されない。The metallic peripheral neutron absorbing material 26 is provided in the neutron absorbing element 18 of the second group which is provided in the inner space of the wing 15 which is separated from the tip structure material 11 by about 1/3 or more of the entire length of the control rod. Not done.

ところで、沸騰水型原子炉では、原子炉停止時に炉心高
さ全長のうち、上方から約１／３までの部分で未臨界度
が特に浅くなる。本発明の原子炉用制御棒はこの点に着
目し、制御棒の上方部分の反応度を大きくし、さらに、
先端部分は制御棒引抜時にも中性子照射されることか
ら、長寿命型中性子吸収板１６を配設したものである。By the way, in a boiling water reactor, the subcriticality becomes particularly shallow in a portion from the upper part to about 1/3 of the total core height when the reactor is stopped. The reactor control rod of the present invention focuses on this point, increases the reactivity of the upper portion of the control rod, and
Since the tip portion is irradiated with neutrons even when the control rod is pulled out, the long-life neutron absorbing plate 16 is provided.

次に、作用を説明する。Next, the operation will be described.

本発明に係る原子炉用制御棒は、原子炉の高出力運転
時、炉心内に残って多量の中性子照射を受ける先端部は
長寿命型中性子吸収板１６が装填されているので、多量
の中性子照射を受けても、その寿命を他部と同等以上と
することができる。In the reactor control rod according to the present invention, the long-lived neutron absorbing plate 16 is loaded in the tip portion that remains in the core and receives a large amount of neutron irradiation during high-power operation of the reactor, so that a large amount of neutrons Even if it receives irradiation, its life can be made equal to or longer than that of other parts.

また、制御棒のウィング内部空間に配列される中性子吸
収要素１７，１８は平板状平缶内に粉末または粒状吸収
材が充填されるので、中性子吸収棒を並列配置した従来
の制御棒に較べ、多量の中性子吸収材をウィング内に配
置することができるとともに、制御棒の先端から約１／
３程度の領域内に配設される第１群の中性子吸収要素１
７の少なくとも側周にハフニウムを主成分とする金属製
周辺中性子吸収材２６が設けられるので、反応度価値を
従来の制御棒より大きくすることができる。したがっ
て、中性子吸収要素１７に充填される吸収材の充填度や
金属製周辺中性子吸収材２６の配設量、その他の緒元
を、炉出力調整用制御棒の反応度価値に見合って選定す
れば、原子炉を安全かつスムーズに停止させることがで
きる。Further, since the neutron absorbing elements 17 and 18 arranged in the wing inner space of the control rod are filled with powder or granular absorbing material in a flat plate can, compared with the conventional control rod in which the neutron absorbing rods are arranged in parallel, A large amount of neutron absorber can be placed in the wing, and about 1 / from the tip of the control rod
First group of neutron absorbing elements 1 arranged in a region of about 3
Since the metallic peripheral neutron absorbing material 26 containing hafnium as a main component is provided on at least the side circumference of 7, the reactivity value can be made larger than that of the conventional control rod. Therefore, if the filling degree of the absorbing material filled in the neutron absorbing element 17, the amount of the metallic peripheral neutron absorbing material 26, and other specifications are selected according to the reactivity value of the control rod for adjusting the reactor power, , The reactor can be stopped safely and smoothly.

さらに、第１群の中性子吸収要素１７Ａの平板状平缶を
ＳＵＳのステンレス鋼製とした場合にも、第６図および
第７図に示すように、平缶１９ａの表面をハフニウムを
主成分とする金属製薄板２８で両側から覆い、この金属
製薄板２８をウィング１５Ａの内部空間内に介装させて
もよい。金属製薄板２８は好ましくは平缶１９ａに取り
付けられる。この金属製薄板２８を平缶１９ａに設けた
場合には、中性子吸収要素の平板状平缶をハフニウムを
主成分とする金属製平缶で製造した場合と、同等の効果
を奏する。Further, even when the flat plate can of the neutron absorbing element 17A of the first group is made of SUS stainless steel, the surface of the can 19a contains hafnium as a main component as shown in FIGS. The metal thin plate 28 may be covered from both sides, and the metal thin plate 28 may be interposed in the internal space of the wing 15A. The thin metal plate 28 is preferably attached to the flat can 19a. When this metal thin plate 28 is provided on the flat can 19a, the same effect as when the flat plate can of the neutron absorbing element is manufactured by the metal flat can whose main component is hafnium is obtained.

次に、原子炉用制御棒の他の実施例を第８図を参照して
説明する。Next, another embodiment of the reactor control rod will be described with reference to FIG.

この実施例に示された原子炉用制御棒はウィング１５Ｂ
の内部空間に列状に配設される中性子吸収要素１７Ｂ，
１８Ｂの構造が一実施例で示したものと基本的に相違
し、他の部材は実質的に異ならないので同じ符号を付
し、説明を省略する。The reactor control rod shown in this embodiment is a wing 15B.
Neutron absorbing elements 17B arranged in rows in the internal space of the
The structure of 18B is basically different from that shown in the embodiment, and other members are substantially the same, and therefore, the same reference numerals are given and the description thereof is omitted.

中性子吸収要素１７Ｂ，１８Ｂは矩形の平板状平缶１９
Ｂ内に、焼結された吸収材２０Ｂを充填させたものであ
る。すなわち、平板状平缶を１９Ｂ内に、ボロンカーバ
イド（Ｂ４Ｃ）の焼結体や、ユーロッピア（Ｅｕ
２Ｏ３）、ガドリニア（Ｇｄ２Ｏ３）、サマリニア（Ｓ
ｍ２Ｏ３）、ディスプロシァ（Ｄｙ２Ｏ３）等の希土類
酸化物焼結体、または、ハフニア（ＨｆＯ２）の焼結体
あるいは前記希土類元素酸化物とＨｆＯ２との混合焼結
体を充填したものである。このように平缶１９Ｂ内に焼
結された吸収材を充填させるため、中性子吸収要素１７
Ｂ，１８Ｂの上端面や下端面、金属製長寿命型中性子吸
収板１６の下端部をウィング１５Ｂの外側端側に向って
下り傾斜させる必要はない。したがって、第１群の中性
子吸収要素１７Ｂ，１８Ｂ間に配設される吸収要素間中
性子吸収材２６ｃを斜めに配設する必要はない。The neutron absorbing elements 17B and 18B are rectangular flat plate-shaped cans 19
B is filled with the sintered absorbent material 20B. That is, a flat plate-shaped can is placed in 19B, and a sintered body of boron carbide (B 4 C) or europia (Eu) is used.
2 O 3 ), gadolinia (Gd 2 O 3 ), summer linear (S
m 2 O 3 ), a dispersion (Dy 2 O 3 ) or other rare earth oxide sintered body, a hafnia (HfO 2 ) sintered body, or a mixed sintered body of the rare earth element oxide and HfO 2 It was done. In order to fill the sintered absorber in the flat can 19B in this manner, the neutron absorbing element 17
It is not necessary to incline the upper and lower end surfaces of B and 18B and the lower end portion of the metal long-life neutron absorbing plate 16 toward the outer end side of the wing 15B. Therefore, it is not necessary to obliquely arrange the inter-absorption element neutron absorbing material 26c arranged between the neutron absorbing elements 17B and 18B of the first group.

しかして、原子炉用制御棒の先端から１／３までの長さ
のウィング１５Ｂの内部空間に配設される第１群の中性
子吸収要素１７Ｂに、ハウニウムを主成分とする金属製
周辺中性子吸収材２６を設けることにより、中性子吸収
要素間に構造材導入に伴う反応度の低下や、タイロッド
側およびウィング外側端に構造材導入に伴う反応度の低
下を抑えることができ、かつ中性子吸収要素１７Ｂの側
周に設けられた金属製周辺中性子吸収材２６により、中
性子吸収用の有効幅を拡大して、反応度を上昇させるこ
とができる。したがって、原子炉の停止時に未臨界度が
浅くなる炉心部分の反応度価値を大きくすることがで
き、炉停止部の未臨界度をより深くし、炉停止を安全か
つ確実に行なうことができる。Then, in the neutron absorbing element 17B of the first group arranged in the internal space of the wing 15B having a length up to 1/3 from the tip of the control rod for a nuclear reactor, the peripheral neutron absorbing metal made mainly of haunium is absorbed. By providing the material 26, it is possible to suppress the decrease in reactivity due to the introduction of the structural material between the neutron absorbing elements and the decrease in the reactivity due to the introduction of the structural material at the tie rod side and the outer end of the wing, and the neutron absorbing element 17B. The peripheral neutron absorbing material 26 made of metal provided on the side circumference of the can increase the effective width for neutron absorption and increase the reactivity. Therefore, it is possible to increase the reactivity value of the core portion where the subcriticality becomes shallow when the nuclear reactor is shut down, deepen the subcriticality of the reactor shutdown portion, and perform the reactor shutdown safely and reliably.

〔発明の効果〕〔The invention's effect〕

以上に述べたように本発明に係る原子炉用制御棒におい
ては、先端構造材に隣接するウィングの内部空間に金属
製長寿命型中性子吸収材を配設し、残りのウィング内部
空間に平板状の中性子吸収要素を複数個列状に配列し、
上記中性子吸収要素のうち、先端構造材側の複数の中性
子吸収要素の少なくとも側周を金属製中性子吸収材で取
り囲み、この中性子吸収材をウィング内部空間に収容し
たから、平板状中性子吸収要素を用いることによって、
中性子吸収材の充填量が従来の制御棒に比べて増大し、
また中性子吸収要素に充填される中性子吸収材の種類や
組成比を適宜選択することにより、反応度価値が大き
く、長寿命型の安全停止用制御棒を提供することができ
る。As described above, in the control rod for a reactor according to the present invention, the metallic long-life neutron absorber is arranged in the inner space of the wing adjacent to the tip structure material, and the remaining wing inner space has a flat plate shape. Arranging multiple neutron absorbing elements of
Among the neutron absorbing elements, at least the side circumference of the plurality of neutron absorbing elements on the tip structure side is surrounded by a metallic neutron absorbing material, and since the neutron absorbing material is housed in the wing internal space, a flat neutron absorbing element is used. By
The filling amount of neutron absorber is increased compared to the conventional control rod,
Further, by appropriately selecting the type and composition ratio of the neutron absorbing material with which the neutron absorbing element is filled, it is possible to provide a long-life type safety stop control rod having a high reactivity value.

また、この原子炉用制御棒は金属製長寿命型中性子吸収
板やハフニウムを主成分とする金属製周辺中性子吸収材
を適所に配設しただけであり、全長にわたって高価で重
量のある金属製中性子吸収材を配置する必要がないの
で、比較的軽量で安価な制御棒とすることができる。In addition, this reactor control rod is only a metal long-life type neutron absorbing plate and a metal peripheral neutron absorbing material whose main component is hafnium are placed in proper places, and expensive and heavy metal neutrons over the entire length. Since it is not necessary to arrange an absorber, the control rod can be made relatively lightweight and inexpensive.

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

第１図は本発明に係る原子炉用制御棒の一実施例を示す
図、第２図は第１図に示した原子炉用制御棒を部分的に
拡大して示す部分断面図、第３図は第１図のIII−III線
に沿う平断面図、第４図は第３図のIV−IV線に沿う断面
図、第５図（Ａ）および（Ｂ）は本発明に係る原子炉用
制御棒に組み込まれる中性子吸収要素と従来の中性子吸
収要素をそれぞれ示す平断面図、第６図は原子炉用制御
棒の第３図に対応する変形例を示す平断面図、第７図は
第６図のVII−VII線に沿う断面図、第８図は本発明に係
る原子炉用制御棒の他の実施例を示す図、第９図（Ａ）
は従来の原子炉用制御棒を示す図、第９図（Ｂ）は第９
図（Ａ）のＢ−Ｂ線に沿う平断面図である。 １０…タイロッド、１１…先端構造材、１４…シース、
１５…ウィング、１６…金属製長寿命型中性子吸収材、
１７，１７Ａ，１７Ｂ，１８，１８Ａ，１８Ｂ…中性子
吸収要素、１９…平缶、２０…吸収材、２１…金属スペ
ーサ、２６…金属製中性子吸収材、２６ａ…内側部中性
子吸収材、２６ｂ…外側端中性子吸収材、２６ｃ…吸収
要素間中性子吸収材、２８…金属製薄板。FIG. 1 is a diagram showing an embodiment of a control rod for a reactor according to the present invention, FIG. 2 is a partial sectional view showing a partially enlarged view of the control rod for a reactor shown in FIG. 1, and FIG. 1 is a plan sectional view taken along line III-III of FIG. 1, FIG. 4 is a sectional view taken along line IV-IV of FIG. 3, and FIGS. 5A and 5B are nuclear reactors according to the present invention. Fig. 6 is a plan sectional view showing a neutron absorbing element and a conventional neutron absorbing element incorporated in a control rod for a nuclear reactor, respectively. Fig. 6 is a plan sectional view showing a modification of the control rod for a nuclear reactor corresponding to Fig. 3, and Fig. 7 is FIG. 6 is a cross-sectional view taken along the line VII-VII, FIG. 8 is a view showing another embodiment of the reactor control rod according to the present invention, and FIG. 9 (A).
Shows a conventional control rod for a nuclear reactor, and FIG.
It is a plane sectional view which follows the BB line of Drawing (A). 10 ... Tie rod, 11 ... Tip structural material, 14 ... Sheath,
15 ... Wing, 16 ... Metal long-life neutron absorber,
17, 17A, 17B, 18, 18A, 18B ... Neutron absorbing element, 19 ... Flat can, 20 ... Absorbing material, 21 ... Metal spacer, 26 ... Metal neutron absorbing material, 26a ... Inner part neutron absorbing material, 26b ... Outer side Edge neutron absorbing material, 26c ... Neutron absorbing material between absorbing elements, 28 ... Metal thin plate.

Claims (7)

【特許請求の範囲】[Claims] 【請求項１】先端構造材と下端構造材とを結合したタイ
ロッドに、深いＵ字状断面のシースを取付けてウィング
を構成し、全体として十字状横断面を有する原子炉用制
御棒において、前記先端構造材に隣接するウィングの内
部空間に金属製長寿命型中性子吸収材を配設し、残りの
ウィング内部空間に平板状の中性子吸収要素を複数個列
状に配列し、上記中性子吸収要素のうち、前記先端構造
材側の複数の中性子吸収要素の少なくとも側周を金属製
周辺中性子吸収材で取り囲み、この中性子吸収材をウィ
ングの内部空間内に収容したことを特徴とする原子炉用
制御棒。1. A control rod for a nuclear reactor having a cross-shaped cross section as a whole, wherein a wing having a deep U-shaped cross section is attached to a tie rod in which a tip structural member and a lower end structural member are joined together. Metal long-life neutron absorbing material is arranged in the inner space of the wing adjacent to the tip structure material, and a plurality of flat neutron absorbing elements are arranged in a row in the remaining inner space of the wing. Among them, at least the peripheral side of the plurality of neutron absorbing elements on the side of the tip structure is surrounded by a metallic peripheral neutron absorbing material, and the neutron absorbing material is housed in the inner space of the wing. . 【請求項２】長寿命型中性子吸収材は、ハフニウムある
いはＨｆ−Ｚｒ合金で形成され、中性子吸収要素は、平
板状の平缶内にボロンカーバイド、あるいはユーロッピ
ア、ガドリニア、サマリニア、ディスプロシャ等の少な
くとも１種類の希土類酸化物とハフニアとの粉末もしく
は粒状吸収材、またはこれらの焼結体などが充填されて
構成された特許請求の範囲第１項に記載の原子炉用制御
棒。2. The long-life neutron absorber is formed of hafnium or Hf-Zr alloy, and the neutron absorbing element is at least boron carbide in a flat plate-shaped can or europia, gadolinia, sama linear, disprosthesis or the like. The control rod for a nuclear reactor according to claim 1, which is configured by being filled with a powder or granular absorbent of one kind of rare earth oxide and hafnia, or a sintered body thereof. 【請求項３】中性子吸収要素の平板状平缶はステンレス
鋼製またはハフニウムを主成分とする金属製である特許
請求の範囲第２項に記載の原子炉用制御棒。3. The reactor control rod according to claim 2, wherein the flat plate can of the neutron absorbing element is made of stainless steel or a metal containing hafnium as a main component. 【請求項４】ウィングの内部空間に収容される中性子吸
収要素のうち、先端構造材から制御棒全長の１／３程度
までの複数の中性子吸収要素の側周にハフニウムを主成
分とする金属製周辺中性子吸収材を設けた特許請求の範
囲第１項に記載の原子炉用制御棒。4. A neutron absorbing element housed in an inner space of a wing, which is made of metal containing hafnium as a main component on a side circumference of a plurality of neutron absorbing elements from a tip structural material to about 1/3 of a control rod total length. The control rod for a nuclear reactor according to claim 1, further comprising a peripheral neutron absorber. 【請求項５】側周が金属製周辺中性子吸収材で取り囲ま
れた中性子吸収要素の表面はハフニウムを主成分とする
金属製薄板で覆われ、この薄板はウィングの内部空間に
介装された特許請求の範囲第１項に記載の原子炉用制御
棒。5. The surface of a neutron absorbing element whose side circumference is surrounded by a peripheral neutron absorbing material made of metal is covered with a thin metal plate containing hafnium as a main component, and the thin plate is interposed in the inner space of the wing. The control rod for a nuclear reactor according to claim 1. 【請求項６】ウィングの内部空間には、金属製長寿命型
中性子吸収板に隣接して、ウィング内部空間の全長の約
１／３の長さに、ハフニウムを主成分とする平板状金属
製平缶内にハフニア、ガドリニア、サマリニア、ディス
プロシャ、ユーロッピア等の酸化物混合焼結体を充填し
た第１群の中性子吸収要素を配置するとともに、この第
１群中性子吸収要素に隣接する下端構造材側には、ステ
ンレス製平板状平缶内にボロンカーバイド焼結体を充填
した第２群の中性子吸収要素を配置した特許請求の範囲
第１項に記載の原子炉用制御棒。6. The inner space of the wing is adjacent to the metal long-life neutron absorbing plate and is made of a plate-shaped metal containing hafnium as a main component and having a length of about 1/3 of the entire length of the inner space of the wing. A first group of neutron absorbing elements filled with a mixed oxide sintered body of hafnia, gadolinia, sumaline, dysproscia, europia, etc. is arranged in a flat can, and a lower end structural material adjacent to the first group neutron absorbing element is arranged. The control rod for a nuclear reactor according to claim 1, wherein a neutron absorbing element of a second group in which a boron carbide sintered body is filled in a flat stainless steel flat can is arranged on the side. 【請求項７】中性子吸収要素の平板状平缶内には溶接可
能な金属スペーサを分散的に配設し、中性子吸収要素の
対向する金属板間の間隔を一定の範囲に保持した特許請
求の範囲第１項に記載の原子炉用制御棒。7. A neutron absorbing element having flat plate-shaped cans in which dispersible metal spacers are dispersively arranged, and the distance between the opposing metal plates of the neutron absorbing element is kept within a certain range. A control rod for a nuclear reactor according to claim 1.
JP60019857A 1985-02-06 1985-02-06 Control rod for nuclear reactor Expired - Lifetime JPH068872B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60019857A JPH068872B2 (en) 1985-02-06 1985-02-06 Control rod for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60019857A JPH068872B2 (en) 1985-02-06 1985-02-06 Control rod for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS61180186A JPS61180186A (en) 1986-08-12
JPH068872B2 true JPH068872B2 (en) 1994-02-02

Family

ID=12010898

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60019857A Expired - Lifetime JPH068872B2 (en) 1985-02-06 1985-02-06 Control rod for nuclear reactor

Country Status (1)

Country Link
JP (1) JPH068872B2 (en)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0833606B2 (en) * 1986-09-19 1996-03-29 コニカ株式会社 Direct positive silver halide color photographic light-sensitive material
JPS63206695A (en) * 1987-02-24 1988-08-25 株式会社日立製作所 Boiling water type reactor core
JP5171151B2 (en) * 2007-08-07 2013-03-27 日立Ｇｅニュークリア・エナジー株式会社 Control rod for boiling water reactor
JP6120492B2 (en) * 2012-05-28 2017-04-26 一般財団法人電力中央研究所 Control rod for thermal neutron reactor
JP2018028472A (en) * 2016-08-18 2018-02-22 一般財団法人電力中央研究所 Control material for thermal neutron reactor control rod and thermal neutron reactor control rod
JP6926234B2 (en) * 2017-12-21 2021-08-25 日立Ｇｅニュークリア・エナジー株式会社 How to cut control rods and used control rods

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60220893A (en) * 1984-04-18 1985-11-05 株式会社日立製作所 Control rod for nuclear reactor

Also Published As

Publication number Publication date
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