JPS61194391A - Control rod for nuclear reactor - Google Patents

Control rod for nuclear reactor

Info

Publication number
JPS61194391A
JPS61194391A JP60035488A JP3548885A JPS61194391A JP S61194391 A JPS61194391 A JP S61194391A JP 60035488 A JP60035488 A JP 60035488A JP 3548885 A JP3548885 A JP 3548885A JP S61194391 A JPS61194391 A JP S61194391A
Authority
JP
Japan
Prior art keywords
wing
control rod
nuclear reactor
neutron
life
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
Application number
JP60035488A
Other languages
Japanese (ja)
Other versions
JPH0580635B2 (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
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Atomic Industry Group 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 Toshiba Corp, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP60035488A priority Critical patent/JPS61194391A/en
Publication of JPS61194391A publication Critical patent/JPS61194391A/en
Publication of JPH0580635B2 publication Critical patent/JPH0580635B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Vibration Dampers (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】 〔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係り、特に中性子吸収材をハイブリ
ッド化し、長寿命化を図るようにした原子炉用制御棒に
関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a control rod for a nuclear reactor inserted into the core of a nuclear reactor such as a boiling water reactor, and in particular hybridizes a neutron absorbing material to achieve a long life. This invention relates to control rods for nuclear reactors that are designed to improve

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

原子炉に用いられる制御棒の中には、4枚のステンレス
鋼製ウィングを結合部を介して一体に結合する一方、ウ
ィングの幅方向に形成された多数の収容穴にボロンカー
バイド(84C)の粉末を充填したものが開発されてい
る。
In the control rod used in a nuclear reactor, four stainless steel wings are joined together via a joint, and boron carbide (84C) is inserted into a large number of accommodation holes formed in the width direction of the wing. A powder-filled version has been developed.

この原子炉用制御棒を沸騰水型原子炉等の熱中性子炉に
使用して炉心部に挿入すると、制御棒は中性子の照射を
受ける。このときの中性子照射量は制御棒の各ウィング
全面にわたって一様ではなく、各ウィングの先端部およ
びウィングの翼端部で強い中性子照射を受ける。このた
め、ウィング先端部および翼端部に充填された84C粉
末は他部のそれに較べ早く劣化し、中性子吸収能力が低
下して核的寿命に達する。したがって、多量に存在する
残りのB4C粉末が核的寿命に達しないうちに、制御棒
を廃棄しなければならなかった。
When this nuclear reactor control rod is used in a thermal neutron reactor such as a boiling water reactor and inserted into the reactor core, the control rod is irradiated with neutrons. At this time, the amount of neutron irradiation is not uniform over the entire surface of each wing of the control rod, and the tip of each wing and the tip of the wing receive strong neutron irradiation. For this reason, the 84C powder filled in the wing tip and blade tip deteriorates more quickly than other parts, and its neutron absorption capacity decreases, reaching the end of its nuclear lifetime. Therefore, the control rods had to be disposed of before the remaining B4C powder, which was present in large quantities, reached its nuclear lifetime.

この点から、本出願人は強い中性子照射を受けるウィン
グの先端部および翼端部位にハフニウム等の長寿命型中
性子吸収材を充填した原子炉用制御棒を提案した(特願
昭59−17355号参照)。ハフニウムは中性子吸収
能力が優れた金属材料で、ボロンカーバイドの3〜6倍
の寿命を有し、中性子照射を受けてもHeガス等を発生
させることがない。このようにすれば、強い中性子照射
を受ける部分が長寿命化されるので制御棒の長寿命化を
図ることができる。
From this point of view, the present applicant proposed a control rod for a nuclear reactor in which the tip and tip portions of the wings, which are exposed to strong neutron irradiation, are filled with a long-life neutron absorbing material such as hafnium (Japanese Patent Application No. 17355/1982). reference). Hafnium is a metal material with excellent neutron absorption ability, has a lifespan 3 to 6 times that of boron carbide, and does not generate He gas or the like even when irradiated with neutrons. In this way, the life of the part that receives strong neutron irradiation is extended, so it is possible to extend the life of the control rod.

ところで−通常の中性子吸収物質であるB4C粉末はボ
ロン−10(”B)が中性子と反応してLi−7やHe
−4を発生させる。発生したヘリウムガスは、中性子照
射時間の経過とともに次第に蓄積され、この蓄積に伴っ
てB4C粉末はスエリングを起こし、ウィングの各収容
穴を膨張させる。また、ヘリウムガスの一部はB4C粉
末から放出されるので収容穴内部にガス圧力が生じ、収
容穴を拡張する方向に作用する。各収容穴はウィング外
側端側に形成される連通孔を介して連絡されているので
、一部の収容穴のガス圧のみが異常に上昇することはな
い。
By the way, in B4C powder, which is a normal neutron absorbing material, boron-10 ("B) reacts with neutrons to form Li-7 and He.
-4 is generated. The generated helium gas gradually accumulates as the neutron irradiation time passes, and as the helium gas accumulates, the B4C powder causes swelling and expands each accommodation hole in the wing. Further, since a part of the helium gas is released from the B4C powder, gas pressure is generated inside the accommodation hole, which acts in a direction to expand the accommodation hole. Since the accommodation holes are connected to each other via the communication hole formed on the outer end side of the wing, the gas pressure in only some of the accommodation holes does not increase abnormally.

しかし、B4C粉末のスエリング現象は、強い中性子照
射を受ける限られた領域で顕著に表われ、その部分の膨
出量が大きくなる。また、現在使用されている原子炉用
制御棒では、各収容穴間のステンレス鋼材の厚さや収容
穴と外表面とのステンレス鋼材の厚さは薄く、例えば1
M程度の厚さに設計されている。しかも、ウィングに形
成される各収容穴は、穿設作業の公差により部分的に一
層薄肉化される虞れがある。
However, the swelling phenomenon of B4C powder is noticeable in a limited area that is exposed to strong neutron irradiation, and the amount of swelling in that area becomes large. In addition, in the control rods for nuclear reactors currently in use, the thickness of the stainless steel material between each accommodation hole and the thickness of the stainless steel material between the accommodation hole and the outer surface are thin, for example, 1.
It is designed to have a thickness of about M. Furthermore, each receiving hole formed in the wing may be partially thinner due to tolerances in the drilling operation.

原子炉用制御棒の各ウィングを構成するステンレス鋼が
各収容大同りで薄肉化されると、制御棒の寿命末期では
B4Cのスエリングに伴う局所的な膨張作用により、各
収容穴間および収容穴と表面との間で亀裂が生じる虞れ
がある。また、ステンレス鋼自体も多量の中性子照射を
受けて脆弱化される一方、84C粒の硬度はステンレス
鋼より大きく、硬いため、B4C粉末粒のスエリング現
象等による何らかの応力発生時に、ウィングが破損し、
機械的損傷を受ける虞れがあった。
When the stainless steel that makes up each wing of a nuclear reactor control rod is thinned at the same time as each accommodation hole, at the end of the control rod's life, due to the local expansion effect caused by the swelling of B4C, the walls between each accommodation hole and the accommodation hole become thinner. There is a risk of cracks forming between the surface and the surface. In addition, while stainless steel itself becomes brittle when exposed to large amounts of neutron irradiation, the hardness of 84C grains is greater than that of stainless steel, so when some stress is generated due to the swelling phenomenon of B4C powder grains, the wings may break.
There was a risk of mechanical damage.

〔発明の目的〕[Purpose of the invention]

本発明は上述した点を考慮してなされたもので、各ウィ
ング内に充填される全ての中性子吸収材がほぼ同時的に
寿命に達するようにして長寿命化を図るとともに、B4
C粉末の局所的スエリングや局所的に強い中性子照射に
よる脆弱化作用を受けても充分な機械的強度を保つこと
ができる長寿命型の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 points, and aims to extend the life of B4 by making all the neutron absorbing materials filled in each wing reach the end of their life at almost the same time.
The object of the present invention is to provide a long-life nuclear reactor control rod that can maintain sufficient mechanical strength even when subjected to weakening effects due to local swelling of C powder or localized strong neutron irradiation.

〔発明の概要〕 本発明に係る原子炉用制御棒は上述した目的を達成する
ために複数の矩形のウィングの内側端を結合部を介して
互いに一体に結合させるとともに、上記ウィングにその
幅方向に穿設された収容穴を、上記ウィングの縦方向に
多数列状に配設し、上記収容穴に中性子吸収材を充填さ
せた原子炉用制御棒において、前記ウィングの挿入方向
先端部に位置される複数の収容穴とウィングの外側端近
傍に長寿命型中性子吸収材を充填して長寿命型中性子吸
収領域を形成し、この中性子吸収領域に隣接して中間中
性子領域が形成され、この中間中性子領域に配置される
各収容穴はウィング内側端側が先細形状に構成されたこ
とを特徴とするものである。
[Summary of the Invention] In order to achieve the above-mentioned object, the control rod for a nuclear reactor according to the present invention integrally connects the inner ends of a plurality of rectangular wings to each other via a connecting portion, and also provides a control rod for a nuclear reactor according to the present invention. In a control rod for a nuclear reactor, in which accommodation holes bored in the wing are arranged in a plurality of rows in the longitudinal direction of the wing, and the accommodation holes are filled with a neutron absorbing material, the control rod is located at the tip of the wing in the insertion direction. A long-life neutron absorbing region is formed by filling the plurality of accommodation holes and the vicinity of the outer end of the wing with a long-life neutron absorbing material, and an intermediate neutron region is formed adjacent to this neutron absorbing region. Each accommodation hole arranged in the neutron region is characterized by having a tapered shape on the inner side of the wing.

〔発明の実施例〕[Embodiments of the invention]

以下、本発明に係る原子炉用制御棒の一実施例について
添付図面を参照して説明する。
EMBODIMENT OF THE INVENTION Hereinafter, one embodiment of a control rod for a nuclear reactor according to the present invention will be described with reference to the accompanying drawings.

本発明に係る原子炉用制御棒10は沸騰水型原子炉等の
熱中性子炉に用いられるもので、複数枚、好適には4枚
の矩形ウィング11を有する。各ウィング11は内側端
が十字状結合部分を備えた結合部材12に一体に結合さ
れ、横断面が十字状をなす制御棒10が基本的に構成さ
れる。制御棒10の先端には操作ハンドル13が設けら
れ、この操作ハンドル13は各ウィング11の先端に一
体あるいは一体的に結合される。
A nuclear reactor control rod 10 according to the present invention is used in a thermal neutron reactor such as a boiling water reactor, and has a plurality of rectangular wings 11, preferably four rectangular wings 11. Each wing 11 is integrally connected at its inner end to a connecting member 12 with a cross-shaped connecting portion, essentially forming a control rod 10 having a cross-shaped cross section. An operating handle 13 is provided at the tip of the control rod 10, and the operating handle 13 is integrally or integrally connected to the tip of each wing 11.

制御棒10の各ウィング11はステンレス鋼等からなる
偏平な金属材料で形成され、内部に幅方向に延びる多数
の収容穴14a、14b、14cが形成される。各収容
穴14はウィング11の縦方向に列状に配列され、数M
程度の(例えば6 rm )の穴径をそれぞれ有する。
Each wing 11 of the control rod 10 is made of a flat metal material such as stainless steel, and has a large number of accommodation holes 14a, 14b, and 14c extending in the width direction formed therein. Each accommodation hole 14 is arranged in a row in the longitudinal direction of the wing 11, and the number M
(e.g. 6 rm).

上記各収容穴14a。Each of the accommodation holes 14a.

14b、14Cは縦方向に延びる連通溝15に互いに連
通される。上記連通溝15はウィング11の外側端近傍
においてその長手方向に延びるように形成される。
14b and 14C communicate with each other through a communication groove 15 extending in the vertical direction. The communication groove 15 is formed near the outer end of the wing 11 so as to extend in the longitudinal direction thereof.

しかして、ウィング11の先端部に形成された複数の収
容穴14a、14bにはハフニウム等の長寿命型中性子
吸収材16a、16bが挿入され、残りの多数の収容穴
14b、14CにはB4C粉末あるいはベレットからな
る中性子吸収材17が充填される。また、ウィング11
の外側端近傍に形成される連通溝15には、ウィング先
端から少なくとも全長の1/2の長さにハフニウム等の
長寿命型中性子吸収材16Cが介装される。長寿命型中
性子吸収材16a〜16Gとしてはハフニウムの他に、
Hf−Zn合金、Aa−1n−Cd合金またはEu2O
3HfO2焼結物あるいはDV2O3  HfO7焼結
物等が用いられる。
Thus, long-life neutron absorbing materials 16a, 16b such as hafnium are inserted into the plurality of accommodation holes 14a, 14b formed at the tip of the wing 11, and B4C powder is inserted into the remaining many accommodation holes 14b, 14C. Alternatively, the neutron absorbing material 17 made of pellets is filled. Also, Wing 11
In the communication groove 15 formed near the outer end of the wing, a long-life neutron absorbing material 16C such as hafnium is interposed at least 1/2 of the total length from the tip of the wing. In addition to hafnium, long-life neutron absorbers 16a to 16G include:
Hf-Zn alloy, Aa-1n-Cd alloy or Eu2O
3HfO2 sintered material, DV2O3 HfO7 sintered material, etc. are used.

このように、原子炉用制御棒10は強い中性子照射を受
ける各ウィング11の先端部(先端から長さ11=5〜
15cjIの領域)および翼端部近傍(幅J!2 =1
.0〜1.5備の領域)に長寿命型中性子吸収材16a
〜16cが充填され、長寿命型中性子吸収領域18が構
成される。長寿命型中性子吸収材168〜16Cは各収
容穴14a、14bや連通溝15形状に対応したロンド
形状あるいはペレット形状に形成される。
In this way, the reactor control rod 10 is exposed to strong neutron irradiation at the tip of each wing 11 (the length from the tip is 11=5~
15cjI area) and near the wing tip (width J!2 = 1
.. Long-life neutron absorber 16a in the region of 0 to 1.5
~16c is filled to form a long-life neutron absorption region 18. The long-life neutron absorbing materials 168 to 16C are formed into a rond shape or a pellet shape corresponding to the shape of each accommodation hole 14a, 14b and communication groove 15.

また、長寿命型中性子吸収棒16a、16bを収納する
収容穴のうち、ウィング先端部に形成される複数の収容
穴14aは、第1図および第2図に示すように、ウィン
グ11の内側端に向う長さが短尺化され、隣接する収容
穴14t)よりウィング11の外側端側で終端している
。すなわち、ウィング11先端部にはその内側端側に収
容穴14aの存在しない中実部分が形成され、中性子の
強い照射に対するウィング11の脆弱化を防止している
。制御棒10の中心軸側、すなわちウィング11の内側
端側は反応度効果が小さいので、反応度の低下は小さい
。また、ウィング先端部の制御棒中心軸側に、ウィング
11の中実部分を形成することにより、中性子吸収効果
が減少し、その結果この部分が隣接する燃料集合体のコ
ーナ部分の制御棒による出力の過度の低下が緩和され、
制御棒移動に伴う、前記コーナ部分の出力インパクトが
軽減される。
Furthermore, among the accommodation holes for accommodating the long-life neutron absorption rods 16a and 16b, the plurality of accommodation holes 14a formed at the tip of the wing are located at the inner end of the wing 11, as shown in FIGS. 1 and 2. The length toward the wing 11 is shortened, and ends at the outer end side of the wing 11 from the adjacent accommodation hole 14t). That is, a solid portion in which the accommodation hole 14a does not exist is formed at the tip end of the wing 11 on its inner end side, thereby preventing the wing 11 from weakening against strong neutron irradiation. Since the reactivity effect is small on the central axis side of the control rod 10, that is, on the inner end side of the wing 11, the decrease in reactivity is small. In addition, by forming a solid part of the wing 11 on the control rod center axis side at the tip of the wing, the neutron absorption effect is reduced, and as a result, this part is used to output power from the control rod at the corner part of the adjacent fuel assembly. The excessive decline in
The output impact at the corner portion due to movement of the control rod is reduced.

さらに、残りの長寿命型中性子吸収棒16bを収容する
複数の収容穴14bは、その先端部が第3図に示すよう
にウィング11の内側端に向って先細形状になるように
構成される。収容穴14bの先端部を先細形状とするこ
とにより、ウィング11の肉厚を大きくして、その機械
的強度を向上させている。
Furthermore, the plurality of accommodation holes 14b for accommodating the remaining long-life neutron absorption rods 16b are configured such that their tips are tapered toward the inner end of the wing 11, as shown in FIG. By tapering the tip of the accommodation hole 14b, the wall thickness of the wing 11 is increased and its mechanical strength is improved.

前記長寿命型中性子吸収領域18に隣接して制鉤棒10
の上部に中間中性子吸収領域19が形成される。この中
間中性子吸収領域19は15cIR〜50cIR程度の
長さj!4を有する。中間中性子吸収領域19に形成さ
れる複数の収容穴14bはウィング内側端側に向って第
4図に示すように先細形状に形成され、ウィング11内
側端部の機械的強度を向上させている。上記各収容穴1
4bは粒径の異なる中性子吸収物質としてボロンカーバ
イド(B  C)粉末粒が充填され、84C粉末粒の充
填密度を向上させている。充填された84C粉末端の開
口端は連通溝15内に収容された長寿命型中性子吸収材
16Cで閉塞される。その際、各収容穴14b、14C
は連通孔2Oで連通され、均圧化されるようになってい
る。
A control rod 10 is provided adjacent to the long-life neutron absorption region 18.
An intermediate neutron absorption region 19 is formed above the neutron absorbing region 19 . This intermediate neutron absorption region 19 has a length j of about 15 cIR to 50 cIR! It has 4. The plurality of accommodation holes 14b formed in the intermediate neutron absorption region 19 are formed in a tapered shape toward the inner end of the wing, as shown in FIG. 4, to improve the mechanical strength of the inner end of the wing 11. Each accommodation hole 1 above
4b is filled with boron carbide (B C) powder grains as a neutron absorbing material having different particle sizes to improve the packing density of the 84C powder grains. The open end of the filled 84C powder end is closed with the long-life neutron absorbing material 16C housed in the communication groove 15. At that time, each accommodation hole 14b, 14C
are communicated through the communication hole 2O, and the pressure is equalized.

また、中間中性子吸収領域19にウィング末端側で隣接
する大部分の収容穴14Cは、第5図に示すようにスト
レート孔形状に構成される。各収容穴14C内に中性子
吸収物質として粒径の異なるB4C粉末粒17が充填さ
れる。この領域の収容穴14Gは加工性を考慮すればよ
く、穴径が異なるように複雑に加工する必要がない。す
なわち、制御棒10は先端からある程度例えば30cI
R程度離れると、中性子照射量も小さくなり、各収容穴
14Gを小穴径とする必要は必ずしもない。中性子照射
量が低下するので、中性子照射によるB4C粉末粒のス
エリング量も小さく、各ウィング11の内側端に作用す
る膨張応力が小さいので、B4C粉末粒の膨張によるウ
ィング破損の問題は考慮しなくてもよい。
Further, most of the accommodation holes 14C adjacent to the intermediate neutron absorption region 19 on the wing end side are configured in a straight hole shape as shown in FIG. Each accommodation hole 14C is filled with B4C powder particles 17 having different particle sizes as a neutron absorbing material. The accommodation holes 14G in this area only need to be formed with consideration to machinability, and there is no need for complicated machining such that the hole diameters are different. That is, the control rod 10 has a certain degree of pressure, for example, 30 cI, from the tip.
When separated by about R, the amount of neutron irradiation also decreases, and it is not necessarily necessary to make each accommodation hole 14G a small hole diameter. Since the amount of neutron irradiation is reduced, the amount of swelling of the B4C powder grains due to neutron irradiation is also small, and the expansion stress acting on the inner edge of each wing 11 is small, so the problem of wing breakage due to expansion of the B4C powder grains does not need to be considered. Good too.

次に、原子炉用制御棒の作用について説明する。Next, the function of the nuclear reactor control rod will be explained.

原子炉用制御棒10を製造する場合には、多数の収容穴
14a、14b、14cを列状に形成した4枚のウィン
グ11の各内側端を結合部材12を介して一体に結合し
、一体構造物とする。各ウィング11を一体化した後に
、各ウィング11に形成された多数の収容穴14a、1
4b、14Cに長寿命型中性子吸収材16a、16bや
B4C粉末粒17からなる中性子吸収物質をそれぞれ充
填させる。
When manufacturing a control rod 10 for a nuclear reactor, the inner ends of four wings 11 each having a large number of accommodation holes 14a, 14b, and 14c formed in a row are joined together via a joining member 12, and then A structure. After integrating each wing 11, a large number of accommodation holes 14a, 1 formed in each wing 11
4b and 14C are respectively filled with a neutron absorbing substance consisting of long-life neutron absorbing materials 16a and 16b and B4C powder particles 17.

各収容穴14a、14b、14cに中性子吸収物質を充
填させた後、縦方向に延びる連通W415内に長寿命型
中性子吸収材16cを充填する。この充填後に各ウィン
グ11の外側端側を内側に包み込むようにかしめ、外側
端を溶接等によりシールドし、原子炉用制御棒10が構
成される。
After each of the accommodation holes 14a, 14b, and 14c is filled with a neutron absorbing material, a long-life neutron absorbing material 16c is filled into the communication W415 extending in the vertical direction. After this filling, the outer end side of each wing 11 is caulked so as to be wrapped inward, and the outer end is shielded by welding or the like, thereby constructing the nuclear reactor control rod 10.

この原子炉用制御棒10は強い中性子照射を受ける各ウ
ィング11の先端部および外側端部が長寿命型中性子吸
収領域18として構成され、長寿命型中性子吸収材16
a、16b、16cが装填されているので、多量の中性
子照射を受けても、その寿命が他領域と同等以上に維持
することができる。このように、強い中性子照射を受け
る部分に、長寿命型中性子吸収材16a〜16Cを配設
することにより、制御棒10の各領域の寿命を平均化さ
せ、全体として長寿命化を図ることができる。
In this nuclear reactor control rod 10, the tips and outer ends of each wing 11, which are exposed to intense neutron irradiation, are configured as long-life neutron absorbing regions 18, and long-life neutron absorbing materials 16
Since the regions a, 16b, and 16c are loaded, even if it receives a large amount of neutron irradiation, its lifespan can be maintained at least equal to that of other regions. In this way, by arranging the long-life neutron absorbers 16a to 16C in the parts that receive strong neutron irradiation, the life of each region of the control rod 10 can be averaged and the life of the control rod 10 can be extended as a whole. can.

また、この原子炉用制御棒10は、タイロッドが不要で
あり、原子炉の炉心部に挿入されると、制御棒10の中
心軸側(長さ11および幅13)の領域に炉水が存在す
るため、中性子照射量が高いが、その部分は中実構造あ
るいは肉厚構造に構成されるので、機械的強度が向上し
、強い中性子照射によるウィング11の脆弱化にも有効
に対応させることができる。
Furthermore, this reactor control rod 10 does not require tie rods, and when inserted into the reactor core, reactor water is present in the area on the central axis side (length 11 and width 13) of the control rod 10. Therefore, the amount of neutron irradiation is high, but since that part is constructed with a solid structure or a thick structure, the mechanical strength is improved and it is possible to effectively cope with weakening of the wing 11 due to strong neutron irradiation. can.

また・比較的強い中性子照射を受ける中間中性子吸収領
域19の各収容穴14bのウィング内側端側は、先細形
状に構成されているので、その部分のウィング11は肉
厚構造となり、機械的強度が向上する。したがって、各
収容穴14bに収容されるB4C粉末粒が比較的強い中
性子照射を受けてスエリングしても、その機械的強度を
有効に保つことができる。
In addition, the inner end of the wing of each accommodation hole 14b of the intermediate neutron absorption region 19, which is subjected to relatively strong neutron irradiation, is configured in a tapered shape, so the wing 11 in that part has a thick structure and its mechanical strength is reduced. improves. Therefore, even if the B4C powder particles accommodated in each accommodation hole 14b undergo relatively strong neutron irradiation and swell, their mechanical strength can be effectively maintained.

なお、本発明の一実施例においては、原子炉用制御棒の
各ウィングに形成される収容穴の穴形状が第2図ないし
第5図に示された例について説明したが、これらの穴形
状に限定されない。例えば、中間中性子吸収領域19に
形成される各収容穴218.21bは、第6図(A)、
(B)および(C)に示す穴形状としてもよい。その際
、第6図(B)および(C)に示すように、収容穴21
a、21bの先端にペレット状の長寿命型中性子吸収材
22a、22bを充填させてもよい。
In addition, in one embodiment of the present invention, the hole shapes of the accommodation holes formed in each wing of the nuclear reactor control rod have been described as shown in FIGS. 2 to 5. but not limited to. For example, each accommodation hole 218.21b formed in the intermediate neutron absorption region 19 is as shown in FIG.
The hole shapes shown in (B) and (C) may also be used. At that time, as shown in FIGS. 6(B) and (C), the accommodation hole 21
Pellet-shaped long-life neutron absorbing materials 22a and 22b may be filled at the tips of the tubes a and 21b.

〔発明の効果〕〔Effect of the invention〕

以上に述べたように本発明に係る原子炉用制御棒は、ウ
ィングの挿入方向先端部に位置される複数の収容穴とウ
ィングの外側端近傍に長寿命型中性子吸収材を充填して
長寿命型中性子吸収領域を形成したから、強い中性子照
射を受ける部分に長寿命型中性子吸収材が配置されて制
御棒各領域の寿命を平均化させ、全体として長寿命化を
図ることができる。
As described above, the nuclear reactor control rod according to the present invention has a long life by filling a plurality of accommodation holes located at the tip of the wing in the insertion direction and near the outer end of the wing with a long-life neutron absorbing material. Since a type neutron absorption region is formed, a long-life neutron absorption material is placed in a portion that receives strong neutron irradiation, which averages out the life of each region of the control rod and extends the life of the control rod as a whole.

また、長寿命型中性子吸収領域に隣接する中間中性子吸
収領域の複数の収容穴はウィング内側端側に向って先細
形状に構成され、その部分のウィングが肉厚構造とされ
るので、比較的強い中性子照射を受けてB4Cがスエリ
ングを起こしても、機械的強度を充分に保つことができ
、ウィングの脆弱を有効的に防止することができる。
In addition, the multiple accommodation holes in the intermediate neutron absorption region adjacent to the long-life neutron absorption region are configured in a tapered shape toward the inner end of the wing, and the wing in that part has a thick structure, making it relatively strong. Even if B4C undergoes swelling due to neutron irradiation, sufficient mechanical strength can be maintained, and wing brittleness can be effectively prevented.

【図面の簡単な説明】[Brief explanation 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
断面図、第2図は第1図に示される原子炉用制御棒をA
−A線に沿って切断したウィングの平断面図、第3図は
第1図のB−B線に沿う平断面図、第4図は第1図のC
−C線に沿う平断面図、第5図は第1図のD−D線に沿
う平断面図、第6図(A)、(B)および(C)は本発
明の原子炉用制御棒のウィングの中間中性子吸収領域に
形成される各収容穴の変形例をそれぞれ示す図である。 10・・・原子炉用制御棒、11・・・ウィング、14
a、14b、14c、21a、21b−・・収容穴、1
5−・・連通溝、16a、16b、16c、22a。 22b・・・長寿命型中性子吸収材、17・・・中性子
吸収材(84C)、18・・・長寿命型中性子吸収領域
、19・・・中間中性子吸収領域。 第1図 第4図 第5図
FIG. 1 is a cross-sectional view showing one embodiment of a nuclear reactor control rod according to the present invention, and FIG.
- A plan sectional view of the wing cut along line A, Figure 3 is a plane sectional view taken along line B-B in Figure 1, and Figure 4 is a plane sectional view taken along line C in Figure 1.
5 is a plan sectional view taken along the line D-D in FIG. FIG. 6 is a diagram illustrating a modification of each accommodation hole formed in the intermediate neutron absorption region of the wing. 10... Nuclear reactor control rod, 11... Wing, 14
a, 14b, 14c, 21a, 21b--Accommodation hole, 1
5-...Communication grooves, 16a, 16b, 16c, 22a. 22b... Long-life neutron absorbing material, 17... Neutron absorbing material (84C), 18... Long-life neutron absorbing region, 19... Intermediate neutron absorbing region. Figure 1 Figure 4 Figure 5

Claims (1)

【特許請求の範囲】 1、複数の矩形のウィングの内側端を結合部を介して互
いに一体に結合させるとともに、上記ウィングにその幅
方向に穿設された収容穴を、上記ウィングの縦方向に多
数列状に配設し、上記収容穴に中性子吸収材を充填させ
た原子炉用制御棒において、前記ウィングの挿入方向先
端部に位置される複数の収容穴とウィングの外側端近傍
に長寿命型中性子吸収材を充填して長寿命型中性子吸収
領域を形成し、この中性子吸収領域に隣接して中間中性
子吸収領域が形成され、この中間中性子吸収領域に配置
される各収容穴はウィング内側端側が先細形状に構成さ
れたことを特徴とする原子炉用制御棒。 2、長寿命型中性子吸収領域はウィングの先端部と、ウ
ィング先端から末端に至るウィング全長の少なくとも1
/2のウィング外側端近傍部とから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。 3、長寿命型中性子吸収材を収容するウィング先端部の
収容穴は、ウィング内側端に向う長さが短尺化され、隣
接する中間中性子吸収領域の収容穴よりウィング外側端
側で終端している特許請求の範囲第1項に記載の原子炉
用制御棒。 4、長寿命型中性子吸収材を収容するウィング先端部の
収容穴は、ウィング内側端に向って先細形状に構成され
た特許請求の範囲第1項に記載の原子炉用制御棒。 5、長寿命型中性子吸収材はハフニウム、Hf−Zn合
金、Ag−In−Cd合金、Eu_2O_3−HfO_
2焼結物あるいはDy_2O_3−HfO_2焼結物で
形成され、収容穴の形状あるいはその近似形状に構成さ
れた特許請求の範囲第1項に記載の原子炉用制御棒。 6、中間中性子吸収領域に引抜方向側で隣接する多数の
収容穴は全長にわたって一様な大きさ形状に構成された
特許請求の範囲第1項に記載の原子炉用制御棒。
[Claims] 1. The inner ends of a plurality of rectangular wings are integrally connected to each other via a connecting portion, and a housing hole formed in the width direction of the wing is formed in the longitudinal direction of the wing. In a nuclear reactor control rod which is arranged in multiple rows and whose accommodation holes are filled with neutron absorbing material, a long life is provided in the plurality of accommodation holes located at the tips of the wings in the insertion direction and near the outer ends of the wings. A long-life neutron absorption region is formed by filling a type neutron absorption material, and an intermediate neutron absorption region is formed adjacent to this neutron absorption region, and each accommodation hole arranged in this intermediate neutron absorption region is located at the inner edge of the wing. A nuclear reactor control rod characterized by having a tapered side. 2. The long-life neutron absorption region is located at the tip of the wing and at least part of the entire length of the wing from the tip of the wing to the end.
2. The control rod for a nuclear reactor according to claim 1, wherein the control rod is comprised of a wing outer end portion of 1/2. 3. The accommodation hole at the tip of the wing that accommodates the long-life neutron absorbing material is shortened in length toward the inner edge of the wing, and terminates closer to the outer edge of the wing than the accommodation hole in the adjacent intermediate neutron absorption region. A control rod for a nuclear reactor according to claim 1. 4. The control rod for a nuclear reactor according to claim 1, wherein the accommodation hole at the tip of the wing that accommodates the long-life neutron absorbing material is tapered toward the inner end of the wing. 5. Long-life neutron absorbers include hafnium, Hf-Zn alloy, Ag-In-Cd alloy, Eu_2O_3-HfO_
2. The control rod for a nuclear reactor according to claim 1, which is formed of a Dy_2O_3-HfO_2 sintered product and configured in the shape of a receiving hole or an approximate shape thereof. 6. The control rod for a nuclear reactor according to claim 1, wherein the large number of accommodation holes adjacent to the intermediate neutron absorption region in the withdrawal direction are configured to have a uniform size and shape over the entire length.
JP60035488A 1985-02-25 1985-02-25 Control rod for nuclear reactor Granted JPS61194391A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60035488A JPS61194391A (en) 1985-02-25 1985-02-25 Control rod for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60035488A JPS61194391A (en) 1985-02-25 1985-02-25 Control rod for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS61194391A true JPS61194391A (en) 1986-08-28
JPH0580635B2 JPH0580635B2 (en) 1993-11-09

Family

ID=12443130

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60035488A Granted JPS61194391A (en) 1985-02-25 1985-02-25 Control rod for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS61194391A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002520575A (en) * 1998-07-02 2002-07-09 ウェスチングハウス アトム アクチボラゲット Absorber and control rod
JP2002533736A (en) * 1998-12-23 2002-10-08 ウェスチングハウス アトム アクチボラゲット Control rod
JP2009058447A (en) * 2007-08-31 2009-03-19 Toshiba Corp Control rod for reactor
CN106384606A (en) * 2016-11-10 2017-02-08 北京凯佰特科技股份有限公司 Emergency shut-down control system for in-hospital neutron irradiation reactor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002520575A (en) * 1998-07-02 2002-07-09 ウェスチングハウス アトム アクチボラゲット Absorber and control rod
JP2002533736A (en) * 1998-12-23 2002-10-08 ウェスチングハウス アトム アクチボラゲット Control rod
JP2009058447A (en) * 2007-08-31 2009-03-19 Toshiba Corp Control rod for reactor
CN106384606A (en) * 2016-11-10 2017-02-08 北京凯佰特科技股份有限公司 Emergency shut-down control system for in-hospital neutron irradiation reactor

Also Published As

Publication number Publication date
JPH0580635B2 (en) 1993-11-09

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