JPH0580635B2 - - Google Patents

Info

Publication number
JPH0580635B2
JPH0580635B2 JP60035488A JP3548885A JPH0580635B2 JP H0580635 B2 JPH0580635 B2 JP H0580635B2 JP 60035488 A JP60035488 A JP 60035488A JP 3548885 A JP3548885 A JP 3548885A JP H0580635 B2 JPH0580635 B2 JP H0580635B2
Authority
JP
Japan
Prior art keywords
wing
control rod
neutron
life
nuclear 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.)
Expired - Lifetime
Application number
JP60035488A
Other languages
Japanese (ja)
Other versions
JPS61194391A (en
Inventor
Kyoshi Ueda
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 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

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
収材をハイブリツド化し、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, a control rod for a nuclear reactor that is hybridized with a neutron absorbing material and has 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
テンレス鋼製ウイングを結合部を介して一体に結
合する一方、ウイングの幅方向に形成された多数
の収容穴にボロン化合物であるボロンカーバイド
(B4C)の粉末を充填したものが開発されてい
る。
Inside the control rod used in a nuclear reactor, four stainless steel wings are joined together through a joint, and boron carbide, a boron compound, is inserted into a large number of accommodation holes formed in the width direction of the wing. A product filled with powder of (B 4 C) 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
は制御棒の各ウイング全面にわたつて一様ではな
く、各ウイングの先端部およびウイングの翼端部
で強い中性子照射を受ける。このため、ウイング
先端部および翼端部に充填されたB4C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。したがつて、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つた。
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 B 4 C powder filled in the wing tip and blade tip deteriorates more quickly than in 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 B 4 C 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
るウイ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 end portions of the wings, which are exposed to strong neutron irradiation, are filled with 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 three to six times longer than 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B4
粉末はボロン−10(10B)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、この蓄積に伴つてB4C粉末はスエリン
グを起こし、ウイングの各収容穴を膨脹させる。
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。各収容穴はウイング
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, B 4 C, which is a normal neutron absorbing material,
The powder is formed by boron-10 ( 10 B) reacting with neutrons to form Li.
-7 and He-4 are generated. The generated helium gas gradually accumulates as the neutron irradiation time passes, and as the helium gas accumulates, the B 4 C powder causes swelling and expands each accommodation hole in the wing.
Further, since a part of the helium gas is released from the B 4 C powder, gas pressure is generated inside the accommodation hole, which acts in the direction of expanding 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 rise 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1mm程度の厚
さに設計されている。しかも、ウイングに形成さ
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 B 4 C powder is noticeable in a limited area that is exposed to strong neutron irradiation, and the amount of swelling in that area becomes large. Furthermore, in the reactor control rods 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, designed to be about 1 mm thick. . 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イングを構成するステン
レス鋼が各収容穴周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
な膨脹作用により、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、B4C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、ウイングが破
損し、機械的損傷を受ける虞れがあつた。
When the stainless steel that makes up each wing of a nuclear reactor control rod is thinned around each accommodation hole, at the end of the control rod's life, due to local expansion due to swelling of B 4 C, the thickness between each accommodation hole and There is a possibility that cracks may occur between the receiving hole and the surface. In addition, while stainless steel itself becomes brittle when exposed to large amounts of neutron irradiation, the hardness of B 4 C grains is larger than that of stainless steel, so when some stress occurs due to the swelling phenomenon of B 4 C powder grains, the wing There was a risk of damage and 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、各ウイ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、B4C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 all the neutron absorbing materials filled in each wing by almost simultaneously reaching the end of their life . 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 or localized strong neutron irradiation.

〔発明の概要〕[Summary of the invention]

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イングの内側端を
結合部を介して互いに一体に結合させるととも
に、上記ウイングにその幅方向に穿設された収容
穴を、上記ウイ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、前記ウイングの挿入方向先
端部に位置される複数の収容穴とウイングの外側
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イ
ング内側端側が先細形状に構成され、上記中間中
性子吸収領域の各収容穴に中性子と反応してスエ
リングを生じる中性子吸収材が充填されたことを
特徴とするものである。
In order to achieve the above-mentioned object, the control rod for a nuclear reactor according to the present invention has inner ends of a plurality of rectangular wings integrally connected to each other via a connecting part, and a hole is bored in the wing in the width direction thereof. In a control rod for a nuclear reactor, in which accommodation holes 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, a plurality of accommodation holes are located at the tip of the wing in the insertion direction. A long-life neutron absorbing material is filled near the outer ends of the holes and wings to form a long-life neutron absorbing region, and an intermediate neutron absorbing region is formed adjacent to this neutron absorbing region. Each accommodation hole arranged has a tapered shape on the inner side of the wing, and each accommodation hole in the intermediate neutron absorption region is filled with a neutron absorbing material that reacts with neutrons and causes swelling. .

〔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枚の矩形ウイング11を有する。
各ウイング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は各ウイング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, basically 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,
This operating handle 13 is integrally or integrally connected to the tip of each wing 11.

制御棒10の各ウイング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はウイング11の縦
方向に列状に配列され、数mm程度の(例えば6
mm)の穴径をそれぞれ有する。上記各収容穴14
a,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はウイング
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。
Each wing 11 of the control rod 10 is formed of a flat metal material such as stainless steel, and has a large number of accommodation holes 14a, 14b, 14c extending in the width direction inside.
is formed. Each housing hole 14 is arranged in a row in the vertical direction of the wing 11, and has a diameter of about several mm (for example, 6 mm).
Each hole has a diameter of mm). Each of the above accommodation holes 14
a, 14b, 14c are communication grooves 15 extending in the vertical direction.
are communicated with each other. 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、ウイング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B4
C粉末あるいはペレツトからなる中性子吸収材1
7が充填される。また、ウイング11の外側端近
傍に形成される連通溝15には、ウイング先端か
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〜16cとしてはハフニ
ウムの他に、Hf−Zr合金、Ag−In−Cd合金また
はEu2O3−HfO2焼結物あるいはDy2O3−HfO2
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 B4 is inserted into the remaining many accommodation holes 14b, 14c.
Neutron absorbing material 1 made of C powder or pellets
7 is filled. Further, in the communication groove 15 formed near the outer end of the wing 11, a long-life neutron absorbing material 16c such as hafnium is interposed at least half the total length from the tip of the wing. In addition to hafnium, the long-life neutron absorbing materials 16a to 16c include Hf-Zr alloy, Ag-In-Cd alloy, Eu2O3 - HfO2 sintered material, Dy2O3 - HfO2 sintered material, etc. is used.

このように、原子炉用制御棒10は強い中性子
照射を受ける各ウイング11の先端部(先端から
長さl1=5〜15cmの領域)および翼端部近傍(幅
l2=1.0〜1.5cm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1
6a〜16cは各収容穴14a,14bや連通溝
15形状に対応したロツド形状あるいはペレツト
形状に形成される。
In this way, the reactor control rods 10 are exposed to strong neutron irradiation at the tip of each wing 11 (region with length l 1 = 5 to 15 cm from the tip) and near the wing tip (width
l 2 =1.0 to 1.5 cm) is filled with long-life neutron absorbing materials 16a to 16c, thereby forming a long-life neutron absorbing region 18. Long-life neutron absorber 1
6a to 16c are formed in a rod shape or 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、ウイ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、ウイング11の内側端に向う長さ
が短尺化され、隣接する収容穴14bよりウイン
グ11の外側端側で終端している。すなわち、ウ
イング11先端部にはその内側端側に収容穴14
aの存在しない中実部分が形成され、中性子の強
い照射に対するウイング11の脆弱化を防止して
いる。一般に、原子炉用制御棒10は、原子炉停
止中は全てのものが炉心に全挿入される。したが
つて、制御棒10の挿入先端部は一般に炉心の端
部に位置することとなり、炉物理理論が教える如
く、原子炉停止への反応度的寄与(反応度効果)
は小さい。さらに横断面十字型に構成された原子
炉用制御棒10の中心軸側、すなわちウイング1
1の内側端側の反応度効果はその他の部分、特に
ウイング11の外側端側のそれに比べて小さい。
このため、ウイング11内側端側の反応度効果が
原子炉停止中では著しく小さく、内側端側の原子
炉用制御棒10の反応度効果の減少は小さい。
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. The length toward the wing 11 is shortened, and the end is closer to the outer end of the wing 11 than the adjacent accommodation hole 14b. That is, the tip of the wing 11 has a housing hole 14 at its inner end.
A solid portion in which no a is present is formed to prevent the wing 11 from weakening against strong neutron irradiation. Generally, all of the nuclear reactor control rods 10 are fully inserted into the reactor core during reactor shutdown. Therefore, the insertion tip of the control rod 10 is generally located at the end of the reactor core, and as taught by reactor physics theory, it contributes reactivity to reactor shutdown (reactivity effect).
is small. Furthermore, the central axis side of the nuclear reactor control rod 10, which has a cross-shaped cross section, that is, the wing 1
The reactivity effect on the inner end side of wing 1 is smaller than that on the other parts, especially on the outer end side of wing 11.
Therefore, the reactivity effect on the inner end side of the wing 11 is extremely small during the reactor shutdown, and the decrease in the reactivity effect on the reactor control rod 10 on the inner end side is small.

また、一般に原子炉運転中、大半の原子炉用制
御棒10は炉心から全引抜とされ、一部の制御棒
10は原子炉の反応度や出力分布を制御するため
に炉心に出入れ制御される。後者の制御棒10
は、原子炉の高出力運転中、一部分引抜状態で炉
心内に挿入されているために、高い中性子束に照
射される。特に制御棒10の挿入先端部とウイン
グ11外側端側の中性子照射量が著しく高くなる
ことは知られている(本願発明者等が特開昭53−
74697号公報で開示)。
Additionally, during reactor operation, most of the reactor control rods 10 are generally completely withdrawn from the core, and some control rods 10 are controlled to be moved in and out of the reactor core in order to control the reactivity and power distribution of the reactor. Ru. latter control rod 10
is inserted into the reactor core in a partially withdrawn state during high-power operation of the reactor, so it is irradiated with a high neutron flux. In particular, it is known that the amount of neutron irradiation at the insertion tip of the control rod 10 and the outer end of the wing 11 becomes significantly high (the inventors of the present application et al.
(Disclosed in Publication No. 74697).

制御棒10の挿入先端部のウイング11の中心
軸側にウイング11の中実部分、すなわちウイン
グ11の構造部材に穴穿けをしないで中性子吸収
材を配置させない部分を形成すると、原子炉運転
中に炉心に中途引抜状態で挿入された中途挿入制
御棒10では、ウイング内側端側がウイング11
外側端側に比べて中性子吸収効果が減少する。そ
の結果、中途挿入制御棒10の挿入先端側のウイ
ング内側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温度の低下が緩和され、原
子炉運転中の制御棒移動に伴う、燃料集合体のコ
ーナ部分の出力インパクトが軽減される。
If a solid part of the wing 11 is formed on the central axis side of the wing 11 at the insertion tip of the control rod 10, that is, a part where no neutron absorbing material is placed without drilling a hole in the structural member of the wing 11, it is possible to In the mid-insertion control rod 10 inserted into the reactor core in a partially withdrawn state, the wing inner end side is the wing 11.
The neutron absorption effect is reduced compared to the outer end side. As a result, the drop in temperature of the output from the control rod at the corner of the fuel assembly adjacent to the wing inner part on the insertion tip side of the mid-inserted control rod 10 is alleviated, and the decrease in the temperature of the output due to the control rod movement during reactor operation is reduced. The output impact at the corners of the assembly 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図に示すようにウイング11の内側端に向つて
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、ウイング
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。
Further, 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. Accommodation hole 14b
By tapering the tip of the wing 11, 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
御棒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15cm〜50
cm程度の長さl4を有する。中間中性子吸収領域1
9に形成される複数の収容穴14bはウイング内
側端側に向つて第4図に示すように先細形状に形
成され、ウイング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14b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(B4
C)粉末粒が充填され、B4C粉末粒の充填密度
を向上させている。充填されたB4C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1
4b,14cは連通孔20で連通され、均圧化さ
れるようになつている。
An intermediate neutron absorption region 19 is formed in the upper part of the control rod 10 adjacent to the long-life neutron absorption region 18 . This intermediate neutron absorption region 19 is 15 cm to 50 cm
It has a length l 4 of the order of cm. Intermediate neutron absorption region 1
The plurality of accommodation holes 14b formed in the wing 9 are tapered toward the inner end of the wing as shown in FIG. 4, thereby improving the mechanical strength of the inner end of the wing 11. Each of the accommodation holes 14b contains boron carbide (B 4
C) The powder grains are packed to improve the packing density of the B 4 C powder grains. The open end of the filled B 4 C powder end is closed with a long-life neutron absorbing material 16c housed in the communication groove 15. At that time, each accommodation hole 1
4b and 14c are communicated with each other through a communication hole 20 so that the pressure is equalized.

また、中間中性子吸収領域19にウイング末端
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14c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30cm程度離
れると、中性子照射量も小さくなり、各収容穴1
4c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B4
粉末粒のスエリング量も小さく、各ウイング11
の内側端に作用する膨脹応力が小さいので、B4
C粉末粒の膨脹によるウイ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 slate hole shape as shown in FIG. Each accommodation hole 14c contains a neutron absorbing material with different particle sizes.
B 4 C powder particles 17 are filled. The accommodation hole 14c in this area may be formed by considering machinability, and there is no need for complicated machining such that the hole diameters are different. That is,
When the control rod 10 moves away from the tip to a certain extent, for example, about 30 cm, the amount of neutron irradiation decreases, and each accommodation hole 1
4c does not necessarily have to be the diameter of the small hole. Since the amount of neutron irradiation decreases, B 4 C due to neutron irradiation
The amount of swelling of powder grains is also small, and each wing 11
Since the expansion stress acting on the inner edge of B 4 is small,
The problem of wing breakage due to expansion of C powder grains does not need to be considered.

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枚のウイング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
イング11を一体化した後に、各ウイング11に
形成された多数の収容穴14a,14b,14c
に長寿命型中性子吸収材16a,16bやB4
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 the control rod 10 for a nuclear reactor, each inner end of the four wings 11 each having a large number of accommodation holes 14a, 14b, and 14c formed in a row is attached to the connecting member 12.
are connected together to form an integral structure. After each wing 11 is integrated, a large number of accommodation holes 14a, 14b, 14c are formed in each wing 11.
Long-life neutron absorbing materials 16a, 16b and B 4 C
Each is filled with a neutron absorbing material consisting of powder grains 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溝15
内に長寿命型中性子吸収材16cを充填する。こ
の充填後に各ウイング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 accommodation hole 14a, 14b, 14c is filled with a neutron absorbing material, a communication groove 15 extending in the vertical direction
A long-life neutron absorbing material 16c is filled inside. 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
ける各ウイング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16a,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 strong neutron irradiation, are configured as long-life neutron absorption regions 18, and long-life neutron absorption materials 16a, 16b, and 16c are loaded. Therefore, even if exposed to large amounts of neutron irradiation,
Its lifespan can be maintained at or above the same level as other areas. 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、タイロツド
が不要であり、原子炉の炉心部に挿入されると、
制御棒10の中心軸部(特にl1とl4部)の領域に
炉水が存在するため、原子炉運転中、中途挿入状
態で使用されている際、高い中性子照射を受ける
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
射によるウイング11の脆弱化にも有効に対応さ
せることができる。
Moreover, this control rod 10 for a nuclear reactor does not require a tie rod, and when inserted into the core of a nuclear reactor,
Since reactor water exists in the area of the central axis of the control rod 10 (particularly l 1 and l 4 ), it is exposed to high neutron irradiation during reactor operation when it is used in the mid-insertion state. Since it has a solid structure or a thick wall structure, the mechanical strength is improved and it is possible to effectively cope with weakening of the wing 11 due to strong neutron irradiation.

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のウイング内側
端側は、先細形状に構成されているので、その部
分のウイング11は肉厚構造となり、機械的強度
が向上する。したがつて、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, since 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, the wing 11 in that part has a thick structure, and its mechanical strength is reduced. improves. Therefore, even if the B 4 C powder particles accommodated in each accommodation hole 14b swell due to relatively strong neutron irradiation, 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
制御棒の各ウイ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21a,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21a,21bの先端に
ペレツト状の長寿命型中性子吸収材22a,22
b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 are explained as shown in FIGS. 2 to 5. but not limited to. For example, the accommodation holes 21a and 21b formed in the intermediate neutron absorption region 19 may have the hole shapes shown in FIGS. 6A, B, and C. At that time, as shown in FIGS. 6B and 6C, pellet-shaped long-life neutron absorbing materials 22a and 22 are placed at the tips of the accommodation holes 21a and 21b.
b may be filled.

〔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、ウイングの挿入方向先端部に位置される複
数の収容穴とウイ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イング内側端
側に向つて先細形状に構成され、その部分のウイ
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、ウイングの
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 B 4 C undergoes swelling under neutron irradiation,
Mechanical strength can be maintained sufficiently, and wing weakness can be effectively prevented.

【図面の簡単な説明】[Brief explanation of the drawing]

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線に沿つて切断したウイング
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
のウイ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……ウイング、
14a,14b,14c,21a,21b……収
容穴、15……連通溝、16a,16b,16
c,22a,22b……長寿命型中性子吸収材、
17……中性子吸収材(B4C)、18……長寿命
型中性子吸収領域、19……中間中性子吸収領
域。
FIG. 1 is a sectional view showing one embodiment of a nuclear reactor control rod according to the present invention, and FIG. 2 is a plane view of a wing obtained by cutting the nuclear reactor control rod shown in FIG. 1 along line A-A. 3 is a plan sectional view along line B-B in FIG. 1, FIG. 4 is a plan sectional view taken along line C-C in FIG. 1, and FIG. 5 is a plan sectional view taken along line C-C in FIG. Planar sectional view along the line,
FIGS. 6A, 6B, and 6C are views showing modified examples of each accommodation hole formed in the intermediate neutron absorption region of the wing of the control rod for a nuclear reactor according to the present invention. 10...Reactor control rod, 11...Wing,
14a, 14b, 14c, 21a, 21b...Accommodation hole, 15...Communication groove, 16a, 16b, 16
c, 22a, 22b...Long-life neutron absorber,
17... Neutron absorbing material (B 4 C), 18... Long-life neutron absorption region, 19... Intermediate neutron absorption region.

Claims (1)

【特許請求の範囲】 1 複数の矩形のウイ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、上記ウイ
ングにその幅方向に穿設された収容穴を、上記ウ
イ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、前記ウイングの挿入方向先端部に位置され
る複数の収容穴とウイ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イング内側端側が
先細形状に構成され、上記中間中性子吸収領域の
各収容穴に中性子と反応してスエリングを生じる
中性子吸収材を充填し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イングの先端部
と、ウイング先端から末端に至るウイング全長の
少なくとも1/2のウイ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イング先
端部の収容穴は、ウイ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
よりウイ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イング先
端部の収容穴は、ウイング内側端に向つて先細形
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−
Zr合金、Ag−In−Cd合金、Eu2O3−HfO2焼結物
あるいはDy2O3−HfO2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つ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。
[Scope of Claims] 1. The inner ends of a plurality of rectangular wings are integrally connected to each other via a connecting portion, and a plurality of accommodation holes are formed in the width direction of the wing in the longitudinal direction of the wing. In a nuclear reactor control rod arranged in a row and having the accommodation holes filled with a neutron absorbing material, a long-life type is provided in the plurality of accommodation holes located at the tips in the insertion direction of the wings and near the outer ends of the wings. A long-life neutron absorption region is formed by filling with a neutron absorption material, an intermediate neutron absorption region is formed adjacent to this neutron absorption region, and each accommodation hole arranged in this intermediate neutron absorption region has a wing inner end side. A control rod for a nuclear reactor, characterized in that it has a tapered shape and that each accommodation hole in the intermediate neutron absorption region is filled with a neutron absorbing material that reacts with neutrons and causes swelling. 2. The nuclear reactor according to claim 1, wherein the long-life neutron absorption region is comprised of the tip of the wing and a portion near the outer edge of the wing that is at least 1/2 of the total length of the wing from the tip of the wing to the end. control rod. 3. A patent in which the accommodation hole at the tip of the wing that accommodates the long-life neutron absorbing material is shortened in length toward the inner end of the wing, and terminates closer to the outer end 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 absorbing material is hafnium, Hf-
The patent claim is made of Zr alloy, Ag-In-Cd alloy, Eu 2 O 3 -HfO 2 sintered product or Dy 2 O 3 -HfO 2 sintered product and configured in the shape of the receiving hole or an approximate shape thereof. A control rod for a nuclear reactor according to scope 1. 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 JPS61194391A (en) 1986-08-28
JPH0580635B2 true 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)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SE514802C2 (en) * 1998-07-02 2001-04-23 Westinghouse Atom Ab Absorbator body and control rod
SE513289C2 (en) * 1998-12-23 2000-08-21 Asea Atom Ab Cross-shaped control rod where the amount of absorber material is smaller in the upper part of the control rod than in its lower part
JP2009058447A (en) * 2007-08-31 2009-03-19 Toshiba Corp Control rod for reactor
CN106384606B (en) * 2016-11-10 2018-10-26 北京凯佰特科技股份有限公司 Hospital's neutron exposure reactor emergency shut-down control system

Also Published As

Publication number Publication date
JPS61194391A (en) 1986-08-28

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