JPS61194392A - Control rod for nuclear reactor - Google Patents

Control rod for nuclear reactor

Info

Publication number
JPS61194392A
JPS61194392A JP60035489A JP3548985A JPS61194392A JP S61194392 A JPS61194392 A JP S61194392A JP 60035489 A JP60035489 A JP 60035489A JP 3548985 A JP3548985 A JP 3548985A JP S61194392 A JPS61194392 A JP S61194392A
Authority
JP
Japan
Prior art keywords
neutron
neutron absorbing
absorbing material
long
rod
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP60035489A
Other languages
Japanese (ja)
Inventor
精 植田
光一 日塔
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 JP60035489A priority Critical patent/JPS61194392A/en
Publication of JPS61194392A publication Critical patent/JPS61194392A/en
Pending 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

  • Vibration Dampers (AREA)
  • Monitoring And Testing Of Nuclear Reactors (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押入さ
れる原子炉用制御棒に係り、特に長寿命型原子炉用制御
棒のハイブリッド構造に関する。
Detailed Description of the Invention (Technical Field of the Invention) The present invention relates to a control rod for a nuclear reactor that is inserted into the core of a nuclear reactor such as a boiling water reactor, and particularly to a control rod for a long-life nuclear reactor. Regarding the hybrid structure of.

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

沸騰水型原子炉等に用いられる制御棒は、第3図および
第4図に示すように構成され、十字状断面を有するタイ
ロッド1の先端および末端に先端構造材2および末端構
造材3をそれぞれ結合させるとともに、上記タイロッド
1の各突出脚に細長いU字状断面のシース4を取付けて
横断面が十字形をなす4枚のウィング5が形成される。
A control rod used in a boiling water reactor etc. is constructed as shown in FIGS. 3 and 4, and has a tip structure member 2 and a terminal structure member 3 at the tip and end of a tie rod 1 having a cross-shaped cross section, respectively. At the same time, a sheath 4 having an elongated U-shaped cross section is attached to each protruding leg of the tie rod 1 to form four wings 5 having a cross-shaped cross section.

各ウィング5内の偏平空間には、多数の長尺な中性子吸
収棒6が介装され、配列される。中性子吸収棒6はボロ
ンカーバイド(84C)等の中性子吸収物質を金属被覆
管内に充填させたものである。
A large number of long neutron absorption rods 6 are interposed and arranged in the flat space within each wing 5. The neutron absorption rod 6 is a metal clad tube filled with a neutron absorption material such as boron carbide (84C).

しかして、原子炉用制御棒が原子炉炉心に挿入され、中
性子の照射を受けると、中性子吸収棒内の中性子吸収物
質は中性子を吸収し、燃焼等による損耗を受け、核反応
生成物質であるヘリウムガス(4He)等のガスが発生
する。このため、制御棒は中性子照射時間の経過ととも
に中性子吸収能力が低下し、金属被覆管内のガス圧が上
昇する。
When a control rod for a nuclear reactor is inserted into a reactor core and is irradiated with neutrons, the neutron-absorbing material inside the neutron-absorbing rod absorbs the neutrons and is subject to wear and tear due to combustion, etc., and becomes a nuclear reaction product. Gas such as helium gas (4He) is generated. For this reason, the control rod's neutron absorption capacity decreases as the neutron irradiation time passes, and the gas pressure within the metal cladding tube increases.

中性子吸収能力が予め定めた値まで低下するに要する中
性子照射時間を核的寿命といい、ガス圧が許容値まで上
昇するに必要な中性子照射時間を機械的寿命と呼んでい
る。
The neutron irradiation time required for the neutron absorption capacity to decrease to a predetermined value is called the nuclear lifetime, and the neutron irradiation time required for the gas pressure to rise to an allowable value is called the mechanical lifetime.

ところで、一本の制御棒に注目した場合、制御棒内に収
容される多数の長尺な中性子吸収棒が全て平等に中性子
照射を受けるわけではない。例えば、原子炉の炉心に制
御棒を部分的に挿入した場合、各ウィングの側縁近傍お
よび先端部分は特に強い中性子照射を受け、この部分の
中性子吸収能力の劣化が著しい。
By the way, when focusing on a single control rod, not all of the many long neutron absorption rods housed within the control rod receive neutron irradiation equally. For example, when a control rod is partially inserted into the core of a nuclear reactor, the vicinity of the side edges and the tip of each wing are particularly exposed to strong neutron irradiation, and the neutron absorption capacity of these parts is significantly deteriorated.

したがって、全ての中性子吸収棒が一様に作られている
従来の原子炉用制御棒では、中性子吸収棒の上端部(先
端部)やウィング側縁に位置する中性子吸収棒が他部ま
たは他の中性子吸収棒より先に中性子吸収能力を失い、
ウィング側縁の中性子吸収棒は他の吸収棒より先に機械
的寿命が損われる。この結果、従来の原子炉用制御棒に
あっては、中性子吸収棒の大部分が使用に耐えるにも拘
らず、原子炉用制御棒を交換しなければならず、制御棒
を有効的に利用することができなかった。
Therefore, in conventional nuclear reactor control rods in which all neutron absorption rods are made uniformly, the neutron absorption rods located at the upper end (tip) or wing side edges of the neutron absorption rods are different from other parts or other control rods. It loses its neutron absorption ability before the neutron absorption rod,
The neutron absorbing rods on the side edges of the wings lose mechanical life before the other absorbing rods. As a result, in conventional nuclear reactor control rods, even though most of the neutron absorption rods are usable, the reactor control rods must be replaced, making effective use of the control rods. I couldn't.

この点から、本出願人は、強い中性子照射を受ける先端
部位に、中性子吸収によってもガスが発生しないハフニ
ウム等からなる長寿命型中性子吸収棒を配設した制御棒
を提案した(特開昭53−74697号および特開昭5
7−173788号公報参照)。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、全体
として原子炉用制御棒の長寿命化を図ることができる。
From this point of view, the applicant proposed a control rod in which a long-life neutron absorbing rod made of hafnium or the like, which does not generate gas even when absorbed by neutrons, is installed at the tip of the rod, which is exposed to strong neutron irradiation (Japanese Patent Laid-Open No. 53 -74697 and JP-A No. 5
7-173788). In this way, the life of the part that receives strong neutron irradiation is extended, so that the life of the reactor control rod can be extended as a whole.

ところが、原子炉用制御棒に例えば84C粉末を充填し
た従来型の中性子吸収棒を使用した場合、使用中に粉末
の下詰まりが生じ、その上端近傍に粉末の存在しない部
分、すなわちボイドが発生する。一般に、84C粉末を
充填した従来型の中性子吸収棒では、SUS製金属被覆
管の先端をSUS製プラグで閉塞し、このプラグに隣接
して金属被覆管内に鉄ウールを長さ数M程度介装してい
る。
However, when a conventional neutron absorption rod filled with, for example, 84C powder is used as a control rod for a nuclear reactor, the bottom of the powder becomes clogged during use, and a void is created near the upper end where no powder exists. . Generally, in a conventional neutron absorption rod filled with 84C powder, the tip of the SUS metal cladding tube is closed with an SUS plug, and a length of iron wool of several meters is inserted into the metal cladding tube adjacent to the plug. are doing.

上記ウールやプラグはB4Cやハフニウム等の中性子吸
収物質に較べて中性子吸収能力が著しく小さいため、非
吸収材部を構成し、上記ウールの下側にボイドが発生す
る。
Since the wool and plug have a significantly lower neutron absorption capacity than neutron absorbing substances such as B4C and hafnium, they constitute a non-absorbing material portion, and voids are generated under the wool.

第5図(A)は原子炉用制御棒に長寿命型中性子吸収材
(ハフニウム板あるいはハフニウム棒)7と従来型のB
4Cを充填した長尺の中性子吸収棒8とを使用したもの
で、両者の境界が一直線上に並び、かつ中性子吸収棒8
の頂部がプラグ9aやウール9bの存在により中性子の
非吸収材部となっている例を示し、この場合の原子炉用
制御棒の中性子束分布は臨界実験データから第5図(B
)に実線で示すように推定される。破線はB4Cの中性
子吸収物質が存在する場合の中性子束分布を示す。符号
9Cはウール部分に形成されるボイド(空隙)を示す。
Figure 5 (A) shows a long-life neutron absorber (hafnium plate or hafnium rod) 7 and a conventional B
A long neutron absorption rod 8 filled with 4C is used, and the boundaries between the two are aligned in a straight line, and the neutron absorption rod 8
Figure 5 (B
) is estimated as shown by the solid line. The broken line shows the neutron flux distribution in the presence of a B4C neutron absorbing substance. Reference numeral 9C indicates a void formed in the wool portion.

臨界実験によると、中性子吸収棒8の非吸収材部中央で
の中性子束の盛上りの大きさは、非吸収材部の長さによ
って変化するが、非吸収材部と84Cとの境界における
中性子束は、非吸収材部が存在しない場合に比べて1.
5〜2倍になり、この中性子束の盛上りは境界の極く近
傍領域にだけ発生することが確認された。
According to criticality experiments, the magnitude of the increase in neutron flux at the center of the non-absorbing material part of the neutron absorbing rod 8 changes depending on the length of the non-absorbing material part, but the neutron flux at the boundary between the non-absorbing material part and 84C The bundle is 1. compared to the case where the non-absorbent part is not present.
It was confirmed that the neutron flux increased by 5 to 2 times, and that this increase in neutron flux occurred only in the region extremely close to the boundary.

そして、このような原子炉用制御棒にボロン−10(”
B)が大幅に減耗されるまで多量の中性子を照射した場
合、非吸収材部に隣接した領域の84Cは局所的に1.
5〜2倍の中性子照射を受け、この中性子照射により核
反応生成物である4H0,71H等が発生し、B4C粉
末粒(ベレット)の膨張によるスエリングが起こる。こ
のため、非吸収材部との境界に近い極く限られた領域で
B4Cの膨張により金属被覆管8aは局所的な臨界実験
では、中性子吸収棒8の非吸収材部の長さを2.5〜5
Q11の間で変えて制御棒表面の中性子束分布を測定し
た。非吸収材部中央での中性子束の盛上りの大きさは、
非吸収材部の長さによって変化するが、非吸収材部と8
4Cとの境界における中性子束は、非吸収材部が存在し
ない場合に比べて1.5〜2倍になる。しかも、この中
性子束の盛上りは境界の極く近傍領域にだけ発生するこ
とが確認された。
Boron-10 ("
When B) is irradiated with a large amount of neutrons until it is significantly depleted, 84C in the region adjacent to the non-absorbing material portion locally becomes 1.
It is irradiated with 5 to 2 times more neutrons, and this neutron irradiation generates nuclear reaction products such as 4H0, 71H, and swelling occurs due to the expansion of the B4C powder grains (vellets). For this reason, in a local critical experiment, the metal cladding tube 8a is caused by the expansion of B4C in a very limited area near the boundary with the non-absorbing material part. 5-5
The neutron flux distribution on the surface of the control rod was measured by changing between Q11. The size of the neutron flux at the center of the non-absorbing material is
Although it varies depending on the length of the non-absorbent part, the length of the non-absorbent part and 8
The neutron flux at the boundary with 4C is 1.5 to 2 times higher than in the case where there is no non-absorbing material portion. Moreover, it was confirmed that this neutron flux increase occurs only in the region very close to the boundary.

そして、このような原子炉用制御棒にボロン−10(”
B)が大幅に減耗されるまで多聞の中性子を照射した場
合、非吸収材部に隣接した領域の84Cは局所的に1.
5〜2倍の中性子照射を受け、この中性子照射により核
反応生成物である7 ・ ’@e、   Ll等が生じ、B4C粉末粒(ペレット
)のスエリングが起こる。このため、非吸収材部との境
界に近い極く限られた領域で84Cの膨張により、金属
被覆管8aは局所的な応力を受けて膨出し、破損したり
する虞れがあった。
Boron-10 ("
When B) is irradiated with a large number of neutrons until it is significantly depleted, 84C in the area adjacent to the non-absorbing material portion locally becomes 1.
It is irradiated with 5 to 2 times more neutrons, and this neutron irradiation produces nuclear reaction products such as 7.'@e, Ll, etc., and swelling of the B4C powder grains (pellets) occurs. For this reason, due to the expansion of 84C in a very limited area near the boundary with the non-absorbent portion, the metal cladding tube 8a is subject to local stress and may bulge and be damaged.

〔発明の目的〕[Purpose 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、長尺
の中性子吸収材と長寿命型中性子吸収材との境界面を凹
凸状に噛合させて、長尺の中性子吸収材の非吸収材部を
中性子吸収物質で取り囲み、中性子束の局所的な盛上り
を抑制することにより、長尺の中性子吸収材の健全性や
信頼性を向上させ、制御棒の長寿命化を図ることができ
るように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 the interface between the elongated neutron absorbing material and the long-life neutron absorbing material is meshed in an uneven manner, and the non-absorbing material of the elongated neutron absorbing material is By surrounding the control rod with a neutron-absorbing material and suppressing the local increase in neutron flux, it is possible to improve the integrity and reliability of the long neutron-absorbing material and extend the life of the control rod. The purpose is to provide control rods for nuclear reactors with

〔発明の概要〕[Summary of the invention]

本発明は、上述した目的を達成するために、タイロッド
の各突出脚にU字状断面のシースを取付けて複数のウィ
ングを構成し、上記タイロッドの挿入先端部に先端構造
材を、また挿入末端部に末端構造材をそれぞれ配置し、
前記先端構造材に隣接する短尺の長寿命型中性子吸収材
とこの中性子吸収材に隣接する長尺の中性子吸収材とを
前記シース内で軸方向に並設した原子炉用制御棒におい
て、前記長尺の中性子吸収材は複数本の中性子吸収棒が
組をなし、各組の中性子吸収棒が長寿命型中性子吸収材
の凹部に係合し、前記長尺の中性子吸収材と長寿命型中
性子吸収材との境界面が凹凸状に噛合するように構成さ
れたことを特徴とするものである。
In order to achieve the above-mentioned object, the present invention includes a plurality of wings by attaching a sheath with a U-shaped cross section to each protruding leg of a tie rod, and a tip structure material at the insertion tip of the tie rod, and a tip structure material at the insertion tip of the tie rod. Place the terminal structural members in each section,
In a nuclear reactor control rod in which a short long-life neutron absorbing material adjacent to the tip structure member and a long neutron absorbing material adjacent to this neutron absorbing material are arranged in parallel in the axial direction within the sheath, the long-life neutron absorbing material The long neutron absorbing material is made up of a plurality of neutron absorbing rods, and each set of neutron absorbing rods engages with the recess of the long-life neutron absorbing material, and the long neutron absorbing material and the long-life neutron absorbing material are connected to each other. It is characterized in that the interface with the material is configured to mesh in an uneven manner.

〔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.

第1図は、沸騰水型原子炉に用いられる本発明の原子炉
用制御棒10を示すものである。制御棒10は横断十字
形をなすタイロッド11を有し、このタイロッド11の
先端および末端側に先端構造材12および図示しない末
端構造材が結合されて一体化される。先端構造材12に
は原子炉用制御棒10の挿入を案内するガイドローラ1
4が備えられるとともに、操作用ハンドル15が設けら
れている。
FIG. 1 shows a nuclear reactor control rod 10 of the present invention used in a boiling water reactor. The control rod 10 has a tie rod 11 having a cross-shaped cross shape, and a tip structure member 12 and an end structure member (not shown) are coupled to the tip and end sides of the tie rod 11 to be integrated. The tip structure member 12 has a guide roller 1 that guides the insertion of the reactor control rod 10.
4 is provided, and an operating handle 15 is also provided.

一方、タイロッド11の各突出脚には深いU字状断面を
有するシース16が取付けられ、横断面が十字形をなす
4枚のウィング17が構成される。
On the other hand, a sheath 16 having a deep U-shaped cross section is attached to each protruding leg of the tie rod 11, forming four wings 17 having a cross-shaped cross section.

ウィング17のシース16内には偏平な内部空間が形成
される。先端構造材12に隣接する内部空間には長寿命
型中性子吸収材18が配設される。
A flat internal space is formed within the sheath 16 of the wing 17. A long-life neutron absorber 18 is disposed in the internal space adjacent to the tip structure member 12 .

この中性子吸収材18はハフニウム(Hf)あるいは@
f−Zn合金等で棒状あるいはプレート状に構成される
。ハフニウムは中性子吸収能力の優れた金属材で、B4
Cの3〜6倍の寿命を有する。
This neutron absorbing material 18 is made of hafnium (Hf) or @
It is made of f-Zn alloy or the like and is shaped like a rod or plate. Hafnium is a metal material with excellent neutron absorption ability, and B4
It has a lifespan 3 to 6 times that of C.

また、長寿命型中性子吸収材18は5〜20atr程度
の短尺の中性子吸収板(中性子吸収棒であってもよい。
Further, the long-life neutron absorbing material 18 may be a short neutron absorbing plate (neutron absorbing rod) of about 5 to 20 atr.

)18aと3m以上の軸方向長さの長尺の中性子吸収棒
(中性子吸収板でもよい。)18bとを有し、これらの
長寿命型中性子吸収材18は強い中性子照射を受ける各
ウィング17の先端部および翼端部に配設される。この
うち、短尺の中性子吸収板18aは先端構造材12に密
接して配置され、長尺の中性子吸収棒18bは各ウィン
グ17の翼端近傍、すなわちシース16の外側端部に必
要に応じて配設される。
) 18a and a long neutron absorption rod (neutron absorption plate may also be used) 18b with an axial length of 3 m or more, and these long-life neutron absorption materials 18 are used for each wing 17 that receives strong neutron irradiation. Arranged at the tip and wing tip. Among these, the short neutron absorbing plate 18a is arranged closely to the tip structure member 12, and the long neutron absorbing rod 18b is arranged near the wing tip of each wing 17, that is, at the outer end of the sheath 16, as necessary. will be established.

さらに、原子炉用制御棒10の偏平空間には長寿命型中
性子吸収材18に隣接して長尺な中性子吸収材19が配
設される。この中性子吸収材19は軸方向長さが異なる
2種類の中性子吸収棒19a、 19bを多数列状に密
接し゛C配設することにより構成される。各中性子吸収
棒19a、19bは、第2図に示すように金属被覆管2
0内にボロンカーバイド(84G)の粉末やベレット等
の中性子吸収物質21が充填され、その先端部に鉄ウー
ル等の金属ウール23が介装され一1先端はプラグ24
により気密に密封される。この金属ウール23およびプ
ラグ24は中性子吸収物質21に較べて中性子吸収能力
が著しく劣り、中性子の非吸収材部25が構成される。
Furthermore, a long neutron absorber 19 is disposed adjacent to the long-life neutron absorber 18 in the flat space of the reactor control rod 10 . This neutron absorbing material 19 is constructed by arranging two types of neutron absorbing rods 19a and 19b having different axial lengths in close proximity in a large number of rows. Each neutron absorption rod 19a, 19b is connected to a metal clad tube 2 as shown in FIG.
A neutron absorbing material 21 such as boron carbide (84G) powder or pellets is filled in the inside of the 0, and a metal wool 23 such as iron wool is interposed at the tip of the neutron absorbing substance 21.
is hermetically sealed. The metal wool 23 and the plug 24 have significantly inferior neutron absorption ability compared to the neutron absorbing material 21, and constitute a neutron non-absorbing material portion 25.

このように、非吸収材部25は各中性子吸収棒19a、
19bの先端部に形成される。
In this way, the non-absorbing material portion 25 includes each neutron absorbing rod 19a,
It is formed at the tip of 19b.

軸方向長さが異なる中性子吸収棒19a、19bのうち
、長さの等しい同一種類の中性子吸収棒が複数本、例え
ば2本づつ組をなし、各組の中性子吸収棒は軸方向長さ
が異なる粗角に交互に配設される。このうち、軸方向長
さが長い中性子吸収棒19aの組は、長寿命型中性子吸
収板18aの切欠凹部26に頂部が挿入されて係合し、
これにより、長尺の中性子吸収材19と長寿命型中性子
吸収材18との境界面は凹凸状(ジクザグ状)に噛合し
ている。
Among the neutron absorbing rods 19a and 19b having different axial lengths, a plurality of neutron absorbing rods of the same type having the same length form a set, for example, two neutron absorbing rods each, and each set of neutron absorbing rods has a different axial length. Arranged alternately at rough corners. Among these, the set of neutron absorption rods 19a having a longer axial length has its top inserted into and engaged with the notch recess 26 of the long-life neutron absorption plate 18a,
As a result, the interface between the elongated neutron absorbing material 19 and the long-life neutron absorbing material 18 mesh in an uneven (zikzag) shape.

しかして、ハフニウム板などの長寿命型中性子吸収板1
8aの凹部に係合する各組の中性子吸収棒19aの頂部
は、周囲がハフニウム等の中性子吸収物質に取り囲まれ
ている。一方、中性子吸収棒19a、19bの頂部には
プラグ24や金属ウール23等からなる非吸収材部25
が形成され、この非吸収材部25の存在により中性子束
は盛り上がろうとする傾向があるが、上記非吸収材部2
5はハフニウム等長寿命型中性子吸収物質で取り囲まれ
ているため、中性子束の盛上り傾向が抑制される。長寿
命型中性子吸収板18aの凹部(切欠部)26に係合し
ていない残りの中性子吸収棒19bの頂部は、隣接する
組の中性子吸収棒19aに充填された84Cによって囲
まれ、中性子束の盛上りが抑制される。この中性子吸収
棒19bは少数本づつ組をなしても、あるいは一本であ
ってもよい。
Therefore, a long-life neutron absorption plate such as a hafnium plate 1
The tops of the neutron absorbing rods 19a of each set that engage with the recesses 8a are surrounded by a neutron absorbing material such as hafnium. On the other hand, a non-absorbing material portion 25 made of a plug 24, metal wool 23, etc. is provided at the top of the neutron absorbing rods 19a, 19b.
is formed, and the neutron flux tends to increase due to the presence of the non-absorbing material portion 25.
Since 5 is surrounded by a long-life neutron absorbing material such as hafnium, the tendency of the neutron flux to increase is suppressed. The tops of the remaining neutron absorption rods 19b that are not engaged with the recesses (notches) 26 of the long-life neutron absorption plate 18a are surrounded by 84C filled in the adjacent set of neutron absorption rods 19a, and the neutron flux is Excitement is suppressed. The neutron absorption rods 19b may be arranged in groups of a small number of rods or may be one rod.

なお、各組をなす中性子吸収棒19a、19bの本数が
多い場合には、それらの頂部非吸収材部25の面積が大
きくなり、これらの非吸収材部25を取り囲む他の中性
子吸収材による中性子抑制効果が低下するので、各組の
中性子吸収棒19a。
Note that when the number of neutron absorption rods 19a, 19b forming each set is large, the area of their top non-absorbing material portions 25 becomes large, and the neutron absorption by other neutron absorbing materials surrounding these non-absorbing material portions 25 increases. Each set of neutron absorption rods 19a because the suppression effect is reduced.

19bの本数は少ない方が望ましい。It is desirable that the number of 19b is small.

次に、作用を説明する。Next, the effect will be explained.

長寿命型中性子吸収材18と長尺の中性子吸収材19と
を組み合せたハイブリッド型原子炉用制御棒10を原子
炉の炉心に挿入すると、制御棒10は中性子の照射を受
ける。この中性子照射を受けた原子炉用制御棒表面の中
性子束2次元分布は、実験によると第1図の左半分に相
対値で示す等高線図で表される。この等高線図からも理
解されるように原子炉用制御棒10は各ウィング17の
先端部と翼端部において特に強い中性子照射を受ける。
When a hybrid reactor control rod 10, which is a combination of a long-life neutron absorber 18 and a long neutron absorber 19, is inserted into the core of a nuclear reactor, the control rod 10 is irradiated with neutrons. According to experiments, the two-dimensional distribution of neutron flux on the surface of a nuclear reactor control rod that has been irradiated with neutrons is represented by a contour map shown in relative values in the left half of FIG. As can be understood from this contour map, the reactor control rod 10 receives particularly strong neutron irradiation at the tips and blade tips of each wing 17.

しかし、この場合、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17の先端部および翼端部に長寿
命型中性子吸収材18を配設したので、中性子照射時間
における中性子吸収能力をほぼ均一化させることができ
、制御棒の長寿命化を図ることができる。
However, in this case, since the reactor control rod 10 is provided with long-life neutron absorbing material 18 at the tip and tip of each wing 17 that is exposed to strong neutron irradiation, the neutron absorption capacity during the neutron irradiation time is approximately reduced. It is possible to achieve uniformity and extend the life of the control rod.

一般に、長寿命型中性子吸収材と長尺の中性子吸収材と
の境界面がジクザクでなく、直線的な場合には、第5図
(B)に示すような中性子束の盛上りが生じ、非吸収材
部25に隣接する84Cの極く限定された範囲でボロン
−10の核分裂反応が進み、その結果、B4Cはスエリ
ングを起し、金属被覆管20を局所的に膨出させ、破損
を生じさぼる虞れがある。しかし、本実施例においては
、長寿命型中性子吸収材18と長尺の中性子吸収棒19
a、19bとの境界面はジクザク状(凹凸状)に噛合し
ており、長尺の中性子吸収棒19a、19bの頂部に形
成される各非吸収材部25は交互に配置され、ハフニウ
ム等の長寿命型中性子吸収材18や他の中性子吸収棒に
充填される84C等の中性子吸収物質で取り囲まれてい
るので、その部分の中性子束の盛上りが抑制される。そ
の結果、長尺の中性子吸収棒19a、19bは頂部付近
のボロン−10の核分裂反応が抑制されるので、金属被
服管20の破損の虞れを解消させることができる。
In general, when the interface between a long-life neutron absorber and a long neutron absorber is not jagged but straight, the neutron flux swells as shown in Figure 5 (B), resulting in a non-conforming The nuclear fission reaction of boron-10 proceeds in a very limited area of 84C adjacent to the absorber section 25, and as a result, B4C causes swelling, locally bulges the metal cladding tube 20, and causes damage. There is a risk of slacking off. However, in this embodiment, the long-life neutron absorbing material 18 and the long neutron absorbing rod 19 are
The boundary surfaces with a and 19b are interlocked in a zigzag shape (uneven shape), and the non-absorbing material portions 25 formed at the tops of the long neutron absorbing rods 19a and 19b are arranged alternately. Since it is surrounded by a neutron absorbing material such as 84C filled in the long-life neutron absorbing material 18 and other neutron absorbing rods, the buildup of neutron flux in that area is suppressed. As a result, the nuclear fission reaction of boron-10 near the tops of the elongated neutron absorption rods 19a and 19b is suppressed, so that the risk of damage to the metal jacketed tube 20 can be eliminated.

なお、本発明の一実施例の説明においては、長寿命型中
性子吸収材として平板状のものを示したが、必ずしもこ
れに限定されず、多数に分割された角棒状あるいは丸棒
状であってもよい。
In the description of one embodiment of the present invention, a long-life neutron absorbing material is shown as a flat plate, but it is not necessarily limited to this, and it may also be in the shape of a rectangular bar or round bar divided into many pieces. good.

また、第1図および第2図に示された長尺の中性子吸収
材は2本の中性子吸収棒が組をなす場合について説明し
たが、中性子吸収棒の配設位置如何によって組を形成す
る中性子吸収棒の本数をウィングの幅方向に変化させて
もよい。タイロッドに隣接する部分では、2本が組をな
すより、一本だけの方が好ましい。
In addition, although the elongated neutron absorbing material shown in FIGS. 1 and 2 has been explained in the case where two neutron absorbing rods form a pair, the neutrons forming the pair may vary depending on the arrangement position of the neutron absorbing rods. The number of absorption rods may be varied in the width direction of the wing. In the area adjacent to the tie rod, it is preferable to have only one tie rod rather than a pair of tie rods.

〔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にお
いては、長尺の中性子吸収材は複数本の中性子吸収棒が
組をなし、各組の中性子吸収棒が長寿命型中性子吸収材
の四部に係合し、前記長尺の中性子吸収材と長寿命型中
性子吸収材との境界面が凹凸状に噛合するように構成さ
れたので、長尺の中性子吸収棒の頂部に形成される非吸
収材部を中性子吸収物質で取り囲み、中性子束の局所的
な盛上りを抑制することができる。したがって、中性子
吸収物質のスエリングを有効的に押え、中性子吸収棒の
部分的な膨張による破損を確実に防止でき、制御棒の健
全性や信頼性を向上させることができ、長寿命化を図る
ことができる。
As described above, in the nuclear reactor control rod according to the present invention, the long neutron absorbing material is made up of a plurality of neutron absorbing rods, and each set of neutron absorbing rods is a long-life neutron absorbing material. Since the interface between the elongated neutron absorbing material and the long-life neutron absorbing material engages with the four parts of the elongated neutron absorbing rod in an uneven manner, By surrounding the non-absorbing material portion with a neutron absorbing material, local increase in neutron flux can be suppressed. Therefore, it is possible to effectively suppress the swelling of the neutron absorbing material, reliably prevent damage due to partial expansion of the neutron absorbing rod, improve the soundness and reliability of the control rod, and extend its life. I can do it.

また、長尺の中性子吸収材は複数本の中性子吸収棒が組
をなし、この中性子吸収棒の組が長寿命型中性子吸収材
の凹部に係合するので、長寿命型中性子吸収材が平板で
形成されている場合、凹部の形成個数が少なくなり、加
工が容易である。
In addition, the long neutron absorbing material is made up of a set of multiple neutron absorbing rods, and this set of neutron absorbing rods engages with the recess of the long-life neutron absorbing material. When the recesses are formed, the number of recesses to be formed is reduced and processing is easy.

【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
部分的縦゛所面図、第2図は上記原子炉用制御棒のウィ
ング内に組み込まれる長尺の中性子吸収棒と長寿命型中
性子吸収材との配置関係を拡大して示す部分図、第3図
は従来の原子炉用制御棒を示す斜視図、第4図は第3図
のIV−IV線に沿う平断面図、第5図(A)および(
B)は従来の原子炉用制御棒内に組み込まれる各中性子
吸収材の配置関係および中性子束分布のに関係をそれぞ
れ示す図である。 10・・・原子炉用制御棒、11・・・タイロッド、1
2・・・先端椛造材、16・・・シース、17・・・ウ
ィング、18・・・長寿命型中性子吸収材、19・・・
長尺の中性子吸収材、19a、19b・・・中性子吸収
棒、20・・・金属被覆管、21・・・中性子吸収物質
、213・・・金属ウール、24・・・プラグ、25・
・・非吸収材部、26・・・凹部。 第1図 第2図 第3図 第4図 第5図 位置 手続補正書(自利 昭和60年 9月22日 事件の表示 昭和60年特許願第35489号 発明の名称 原子炉用制御棒 補正をする者 (ほか1名) 5゜ 6、補正の内容 (1)明細書中筒7頁第7行記載の「局所的な」の後に
「応力を受けて膨出し、破損したりする恐れがあった。 」を挿入する。
FIG. 1 is a partial vertical view showing one embodiment of a nuclear reactor control rod according to the present invention, and FIG. 2 shows a long neutron absorption rod incorporated in the wing of the nuclear reactor control rod. Fig. 3 is a perspective view showing a conventional nuclear reactor control rod, and Fig. 4 is a cross-sectional view taken along line IV-IV in Fig. 3. Figure 5 (A) and (
B) is a diagram showing the arrangement relationship of each neutron absorbing material incorporated in a conventional control rod for a nuclear reactor and the relationship of neutron flux distribution. 10... Nuclear reactor control rod, 11... Tie rod, 1
2...Tip construction material, 16...Sheath, 17...Wing, 18...Long-life neutron absorbing material, 19...
Long neutron absorbing material, 19a, 19b... Neutron absorbing rod, 20... Metal clad tube, 21... Neutron absorbing material, 213... Metal wool, 24... Plug, 25...
...Non-absorbent portion, 26...Concave portion. Fig. 1 Fig. 2 Fig. 3 Fig. 4 Fig. 5 Location procedure amendment (JIRI Indication of the September 22, 1985 incident 1985 patent application No. 35489 Name of the invention Correction of control rods for nuclear reactors) (and one other person) 5゜6. Contents of the amendment (1) In the 7th line of page 7 of the specification, after the word ``local'' there is a statement that ``there is a risk of swelling and damage due to stress.'' ” is inserted.

Claims (1)

【特許請求の範囲】 1、タイロッドの各突出脚にU字状断面のシースを取付
けて複数のウィングを構成し、上記タイロッドの挿入先
端部に先端構造材を、また挿入末端部に末端構造材をそ
れぞれ配置し、前記先端構造材に隣接する短尺の長寿命
型中性子吸収材とこの中性子吸収材に隣接する長尺の中
性子吸収材とを前記シース内で軸方向に並設した原子炉
用制御棒において、前記長尺の中性子吸収材は複数本の
中性子吸収棒が組をなし、各組の中性子吸収棒が長寿命
型中性子吸収材の凹部に係合し、前記長尺の中性子吸収
材と長寿命型中性子吸収材との境界面が凹凸状に噛合す
るように構成されたことを特徴とする原子炉用制御棒。 2、長尺の中性子吸収材は軸方向長さが異なる複数種類
の中性子吸収棒を備え、シース内の偏平空間に列状に並
設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、長尺の中性子吸収材は軸方向長さが異なる2種類の
中性子吸収棒を備え、同一種の中性子吸収棒を2本づつ
組をなして交互に並設した特許請求の範囲第1項に記載
の原子炉用制御棒。 4、中性子吸収棒の先端部にプラグや金属ウール等の中
性子の非吸収材部が形成され、この非吸収材部は長寿命
型中性子吸収材や隣接する中性子吸収棒内の中性子吸収
物質で周りが取り囲まれた特許請求の範囲第2項または
第3項に記載の原子炉用制御棒。
[Claims] 1. A sheath with a U-shaped cross section is attached to each protruding leg of the tie rod to form a plurality of wings, and a tip structure material is attached to the insertion tip of the tie rod, and a terminal structure material is attached to the insertion end. and a short long-life neutron absorbing material adjacent to the tip structure member and a long neutron absorbing material adjacent to this neutron absorbing material are arranged in parallel in the axial direction within the sheath. In the rod, the elongated neutron absorbing material is made up of a plurality of neutron absorbing rods, each group of neutron absorbing rods is engaged with a recessed portion of the long-life neutron absorbing material, and the elongated neutron absorbing material and A control rod for a nuclear reactor, characterized in that an interface with a long-life neutron absorber is configured to mesh in an uneven manner. 2. For use in a nuclear reactor according to claim 1, the long neutron absorbing material includes a plurality of types of neutron absorbing rods having different axial lengths, and is arranged in a row in a flat space within the sheath. control rod. 3. The elongated neutron absorbing material is provided with two types of neutron absorbing rods having different axial lengths, and the neutron absorbing rods of the same type are arranged alternately in sets of two, as claimed in claim 1. A control rod for a nuclear reactor described in . 4. A neutron non-absorbing material part such as a plug or metal wool is formed at the tip of the neutron absorbing rod, and this non-absorbing material part is surrounded by a long-life neutron absorbing material or a neutron absorbing material in an adjacent neutron absorbing rod. A control rod for a nuclear reactor according to claim 2 or 3, in which:
JP60035489A 1985-02-25 1985-02-25 Control rod for nuclear reactor Pending JPS61194392A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60035489A JPS61194392A (en) 1985-02-25 1985-02-25 Control rod for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60035489A JPS61194392A (en) 1985-02-25 1985-02-25 Control rod for nuclear reactor

Publications (1)

Publication Number Publication Date
JPS61194392A true JPS61194392A (en) 1986-08-28

Family

ID=12443158

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60035489A Pending JPS61194392A (en) 1985-02-25 1985-02-25 Control rod for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS61194392A (en)

Similar Documents

Publication Publication Date Title
JPS63253290A (en) Thin-wall channel
JPH0441797B2 (en)
JPS6224755B2 (en)
JPS61194392A (en) Control rod for nuclear reactor
US6226340B1 (en) Hermaphroditic absorber loading for higher worth control rods
JPS5873896A (en) Fissionable fuel assembly for low speed reactor
JPH036493A (en) Reactor control rod
JPH0345354B2 (en)
US20140098925A1 (en) Control rod for nuclear reactor and method of manufacturing control rod
JPS61189488A (en) Control rod for nuclear reactor
JP2004212372A (en) Fuel assembly of nuclear reactor
JPS62187284A (en) Control rod for nuclear reactor
JPH021277B2 (en)
JPS59132389A (en) Fuel assembly
JP7176999B2 (en) Fuel elements, fuel assemblies and cores
JPS6276491A (en) Control rod for nuclear reactor
JP4351798B2 (en) Fuel assemblies and reactors
JP2878813B2 (en) Reactor control rod
JP3080775B2 (en) Reactor control rod
JP2010014493A (en) Boiling water reactor and control rod
JPS61180187A (en) Control rod for nuclear reactor
JPH0220077B2 (en)
JPH041593A (en) Fuel assembly
JPS6110239Y2 (en)
JPS62130387A (en) Control rod for nuclear reactor