JPS62187284A - Control rod for nuclear reactor - Google Patents

Control rod for nuclear reactor

Info

Publication number
JPS62187284A
JPS62187284A JP61029005A JP2900586A JPS62187284A JP S62187284 A JPS62187284 A JP S62187284A JP 61029005 A JP61029005 A JP 61029005A JP 2900586 A JP2900586 A JP 2900586A JP S62187284 A JPS62187284 A JP S62187284A
Authority
JP
Japan
Prior art keywords
neutron
long
absorbing material
control rod
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.)
Granted
Application number
JP61029005A
Other languages
Japanese (ja)
Other versions
JPH0816716B2 (en
Inventor
精 植田
関口 善之
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 JP61029005A priority Critical patent/JPH0816716B2/en
Publication of JPS62187284A publication Critical patent/JPS62187284A/en
Publication of JPH0816716B2 publication Critical patent/JPH0816716B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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、特に長スを命型原子炉m制
御211棒のハイブリッドM4造にl3II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, 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. Control 211 rod hybrid M4 construction l3II.

〔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4図および
第5図に示ずように構成され、十字状断面を右するタイ
ロッド1の先端および末端に先端構造材2 J3よび末
端構造材3をそれぞれ結合さ゛ぜるとと6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。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(B4C”)等の中性子吸収物質を
金属被覆管内に充填さけた乙のである。
A control rod used in a boiling water reactor, etc. is constructed as shown in FIGS. 4 and 5, with a tie rod 1 having a cross-shaped cross section, and a tip structure member 2 J3 and a terminal structure member attached to the tip and end of the tie rod 1. When 3 and 6 are connected to each other, 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. A large number of long neutron absorption rods 6 are interposed and arranged in the flat space within each wing 5. Neutron absorption rod 6
In this case, a neutron-absorbing substance such as boron carbide (B4C'') is filled into the metal clad tube.

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10耗を受【ノ、核
反応生成物質であるヘリウムガス(’He)等のガスが
発生する。このため、制御棒は中性子照射11′5間の
経過とともに中性子吸収能ツノが低下し、金属被覆管内
のガス圧が上4する。
When a nuclear reactor control rod is inserted into a reactor core and is irradiated with neutrons, the neutron-absorbing material inside the neutron-absorbing rod absorbs the neutrons and undergoes wear due to combustion, etc. Gas such as helium gas ('He), which is a substance, is generated. Therefore, the neutron absorption capacity of the control rod decreases as the neutron irradiation period 11'5 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11i間を核的寿命といい、ガス圧が許容値ま
で上界するに必要な中性子照射時間を機械的11’命と
呼んでいる。
The neutron irradiation time 11i 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 11' life.

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イ!中性子吸収(仝が全て平等に中
性子照射を受c)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J3よび先端部分は特に強い中性子照DJを受け、
この部分の中性子吸収能力の劣化が暑しい。
By the way, when focusing on a single control rod, there are many long rods housed within the control rod! Neutron absorption (not all objects receive neutron irradiation equally). For example, when a control rod is partially inserted into the core of a nuclear reactor, the side edge J3 and the tip of each wing receive particularly strong neutron radiation DJ.
The deterioration of the neutron absorption capacity of this part is disturbing.

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8Il)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まっ先に
寿命が損われる。
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 8Il) of the neutron absorption rod or the wing side edges are The neutron-absorbing rods lose their neutron-absorbing ability before the neutron-absorbing rods, and the neutron-absorbing rods on the side edges of the wings lose their lifespan before the other absorbing rods.

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、原子か用制御
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。
As a result, in conventional nuclear reactor control rods, even though most of the neutron absorption rods are usable, the atomic 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B4C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、ずなわちボイドが発生する。一般に、B4C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畝ウールを長さ数履程痘介装してい
る。
However, when a conventional neutron absorption rod filled with, for example, B4C powder is used as a control rod for a nuclear reactor, the bottom of the powder becomes clogged during use, and a void where no powder exists near the upper end of the rod. Occur. Generally, in a conventional neutron absorption rod filled with B4C powder, the tip of the SUS metal clad tube is closed with an SUS plug, and a few threads of ridged wool are inserted into the metal clad tube adjacent to the plug. I am wearing it.

さらに、上記鉄ウールやプラグは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茗しく小さ
いため、非吸収材部を構成し、上記鉄Cクールの下側に
ボイドが発生する。
Furthermore, since the iron wool and the plug have a considerably 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 iron C cool.

第6図(△)は原子炉用制御棒に長寿命型中竹子吸収材
(ハフニウム板あるいはハフニウム棒)7と従来型のB
、Cを充填した長尺の中性子吸収棒8とを使用したしの
で、両者の境界が隙間1を介して一直線上に並び、かつ
中性子吸収棒8の頂部がプラグ9aや鉄ウール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6図(B)に実線へで示すように推定される。
Figure 6 (△) shows a long-life medium bamboo absorber (hafnium plate or hafnium rod) 7 and a conventional B
, and a long neutron absorbing rod 8 filled with C, the boundaries between the two are aligned in a straight line through the gap 1, and the top of the neutron absorbing rod 8 is formed by the presence of the plug 9a and the iron wool 9b. An example is shown in which the control rod is a non-absorbing material for neutrons, and the neutron flux distribution of the reactor control rod in this case is estimated from the critical experiment data as shown by the solid line in FIG. 6(B).

破FJBはB4Cまたはハフニウム(Hf )が存在す
る場合の中性子分布曲線を示し、一点鎖線Cは隙間オが
存在しない場合の中性子分布曲線を示す。符号9Gは鉄
ウール部分に形成されるボイド(空隙)を示し、隙間l
は原子炉の中で制御棒を長期間使用する場合、中性子吸
収材7および8が中性子照射を受け、いわゆる照射成長
する場合に対する逃げしろである。
Broken FJB shows the neutron distribution curve when B4C or hafnium (Hf) is present, and dashed line C shows the neutron distribution curve when gap O does not exist. The code 9G indicates a void formed in the iron wool part, and the gap l
When the control rod is used in a nuclear reactor for a long period of time, the neutron absorbing materials 7 and 8 are exposed to neutron irradiation, which is a protection against the so-called irradiation growth.

臨界実験によると、中性子吸収棒8の非吸収材部りの中
央での中性子束の盛上りの大ぎさは、非吸収材部りの長
さによって変化するが、非吸収材部りとB4Cどの境界
にお【ノる中性子束は、非吸収U 7Js Dが存在し
ない場合に比べて1.5〜2償になり、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ずることが確認
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 difference between the non-absorbing material part and the B4C The neutron flux at the boundary is 1.5 to 2 times higher than in the case where there is no non-absorbing U 7Js D, and this increase in neutron flux is likely to occur only in the very vicinity of the boundary. confirmed.

そして、このような原子炉用制12II棒にボロン−1
0(10B)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B4Cは局所
的に1.5〜2イ8の中性子照射を受【プ、この中性子
照射により核反応生成物である4   1 。
Then, boron-1 was added to the 12II rod used in such a nuclear reactor.
When 0 (10B) is irradiated with a large amount of neutrons until it is significantly depleted, B4C in the area adjacent to the non-absorbing material part is locally irradiated with 1.5 to 2-8 neutrons, and this neutron 4 1 is a nuclear reaction product upon irradiation.

t−Ie 、  L I Wが発生し、B4C粉末粒(
ベレッ]・)の膨張にJ:るスエリングが起こる。この
ため、非吸収材部りどの境界に近い撞く限られた領域で
B、Cの膨張により金属被覆管88は局所的な応力を受
りて膨出し、破損したりする恐れがあ−)だ。
t-Ie, LIW are generated, and B4C powder grains (
Swelling occurs due to the expansion of J:. Therefore, due to the expansion of B and C in a limited area near the boundary of the non-absorbing material part, the metal cladding tube 88 is subject to local stress and may bulge and break. .

臨界実験では、中性子吸収棒8の非吸収材部りの長さを
1 cm〜5α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、非吸収材部りの長さによって変化するが、非吸
収材部りとB4Cとの境界におりる中性子束は、非吸収
材部の長さが1゜5 cm以上で、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[りは境界の極く近IZ領域にだけ発生する
ことが確認された。
In the critical experiment, the length of the non-absorbing material portion of the neutron absorption rod 8 was varied between 1 cm and 5α, and the neutron flux distribution on the surface of the control rod was measured. The size of the neutron flux at the center of the non-absorbing material changes depending on the length of the non-absorbing material, but the neutron flux that falls at the boundary between the non-absorbing material and B4C is The length of the absorbent portion is 1°5 cm or more, and the length is 1.5 to 2 times that of the case where the non-absorbent portion is not present. Furthermore, it was confirmed that this neutron flux surge occurs only in the IZ 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’l]e!、  Ll等が生じ、B4
C粉末粒あるいはベ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掻く限られた領域でB
4Cの膨張により、金属被覆管8aは局所的な応力を受
番ノで膨出し、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 receives 5 to 2 times more neutron irradiation, and this neutron irradiation produces nuclear reaction products 'l]e! , Ll, etc. occur, and B4
C Swelling of powder grains or pellets occurs. Therefore, B in a limited area near the boundary with the non-absorbent part
Due to the expansion of the metal cladding tube 4C, the metal cladding tube 8a may swell due to local stress and may 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
の中性子吸収材の頂部に短尺軽皐物の長寿命型中性子吸
収材を当接させて隙間に基づく中性子束の局所的な盛上
りを抑制し、長尺の中性子吸収材の健全性や信頼性を向
上させて制御棒の長野白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 involves locally increasing the neutron flux based on the gap by bringing a long-life neutron absorbing material made of short, lightweight fiber into contact with the top of a long neutron absorbing material. It is an object of the present invention to provide a control rod for a nuclear reactor, which suppresses the rise of neutrons, improves the soundness and reliability of a long neutron absorber, and makes it possible to prevent Nagano whitening of the control rod.

〔発明の概要〕[Summary of the invention]

本発明に係る原子炉用制御棒は、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、前記短
尺の長寿命型中性子吸収材は制御棒の軸方向に分割され
、分割された末端側の長寿命型中性子吸収材は短尺軽量
物とされて前記長尺の中性子吸収材に当接して配置され
たことを特徴とするものである。
The control rod for a nuclear reactor according to the present invention has a U-shaped cross-section sheath attached to each protruding leg of a 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 tip structure material is attached to the insertion end of the tie rod. Atoms in which a short long-life neutron absorbing material adjacent to the tip structural material and a long neutron absorbing material adjacent to this neutron absorbing material are arranged in parallel in the axial direction within the sheath. In a reactor control rod, the short long-life neutron absorbing material is divided in the axial direction of the control rod, and the long-life neutron absorbing material at the end of the division is made short and lightweight to absorb the long neutrons. It is characterized by being placed in contact with the material.

〔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。図において、左半分は
実験的に求めた制御棒表面の中性子束分布を等0線で示
すもので、この中性子束分布図から、制御棒10のどの
位置の中性子吸収材が高くなるかが判別でさる。制御棒
10は横断面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。
FIG. 1 shows a nuclear reactor control rod 10 of the present invention used in a boiling water reactor. In the figure, the left half shows the experimentally determined neutron flux distribution on the control rod surface using iso-zero lines. From this neutron flux distribution map, it can be determined at which position on the control rod 10 the neutron absorbing material is high. It's a monkey. The control rod 10 has a tie rod 11 having a cross-shaped cross section, 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.

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14が備えられる。
The tip structure member 12 is provided with guide rollers 14 that guide insertion of the reactor control rod 10.

fJ号15は制御棒10の操作用ハンドル15である。fJ number 15 is a handle 15 for operating the control rod 10.

一方、タイロッド11の各突出脚には深い()字状断面
を右するシース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 ( )-shaped cross section is attached to each protruding leg of the tie rod 11, and four wings 17 having a cross-shaped cross section are formed.

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゛IM造材12に隣接する内部空間には長
寿命型中性子吸収材18a、18bがウィング17の軸
方向に分割されて配設される。この中性子吸収材18a
、18bはハフニウム(I−1f)あるいはHf’−Z
r合金等で棒状あるいはブレート状に構成される。ハフ
ニウムは中性子吸収能力の1■れた金属材で、84Cの
3〜6倍の寿命を右する。
A flat internal space is formed within the sheath 16 of the wing 17. Long-life neutron absorbing materials 18a and 18b are divided in the axial direction of the wing 17 and arranged in the internal space adjacent to the tip IM material 12. This neutron absorbing material 18a
, 18b is hafnium (I-1f) or Hf'-Z
It is made of r-alloy or the like and is shaped like a rod or a plate. Hafnium is a metal material with a neutron absorption capacity of 1.5 mm, and has a lifespan 3 to 6 times that of 84C.

また、長寿命型中性子吸収材18a、18bはその合計
長さく挿入方向の長さ)が5〜30cm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、、)であり
、前記ウィング17のVI)2端には、1.5m以上の
軸方向長さを有する長尺の長寿命型中性子吸収棒(中性
子吸収板でらJ:い。)18Cが複数本配列される。こ
れらの長寿命型中性子吸収材18a〜18cは強い中性
子照射を受ける各ウィング17の先端部J3よび翼端部
にそれぞれ配設される。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、タイ「1
ツド11の先端突起に係合される。一方、長尺の中性子
吸収棒18Cは各ウィング17の翼端近傍、ずなわらシ
ース16の外側端部に必要に応じて配設される。
Further, the long-life neutron absorbers 18a and 18b are short neutron absorbing plates (which may be neutron absorbing rods) with a total length (length in the insertion direction) of about 5 to 30 cm, and the wing 17, VI) A plurality of long-life neutron absorption rods (neutron absorption plates) 18C each having an axial length of 1.5 m or more are arranged. These long-life neutron absorbers 18a to 18c are disposed at the tip J3 and the blade tip of each wing 17, which are exposed to strong neutron irradiation. Among these, the short neutron absorption plate 18a is arranged closely to the tip structure member 12, and the tie "1"
It is engaged with the tip projection of the tube 11. On the other hand, a long neutron absorption rod 18C is disposed near the tip of each wing 17 and at the outer end of the sheath 16 as necessary.

先端の長寿命型中性子吸収材18aの末端側に配設され
る長寿命型中性子吸収材18bは挿入方向のt+ざが1
〜3 cm程度の短尺軽tH物とされる。
The long-life neutron absorber 18b disposed on the distal end side of the long-life neutron absorber 18a at the tip is t + 1 in the insertion direction.
It is considered to be a short and light tH object of about 3 cm.

この中性子吸収材18bの引1友側に1lAi接して長
尺な中性子吸収棒19が配設される。中性子吸収棒19
は複数本がウィング17の幅方向に密接して配設され、
第2図に示り°ようにその金属被覆管20内にボロンカ
ーバイド(B4C)の粉末やペレット笠の中性子吸収物
質21が充填される。中性子吸収棒19の先端部には鉄
ウール等の金属ウール22が介装され、先端はプラグ2
3にJ:り気密に密封される。この金属ウール22J3
よびプラグ23は中性子吸収物質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D1が形成される
A long neutron absorbing rod 19 is disposed in contact with 1 lAi on the pulling side of the neutron absorbing material 18b. Neutron absorption rod 19
A plurality of these are closely arranged in the width direction of the wing 17,
As shown in FIG. 2, the metal cladding tube 20 is filled with a neutron absorbing material 21 such as boron carbide (B4C) powder or a pellet cap. A metal wool 22 such as iron wool is interposed at the tip of the neutron absorption rod 19, and a plug 2 is inserted at the tip.
3. It is hermetically sealed. This metal wool 22J3
The plug 23 has significantly inferior neutron absorption ability compared to the neutron absorbing material, and a neutron non-absorbing material portion D1 is formed.

一方、先端の長寿命型中性子吸収材18aと次の短尺中
性子吸収材18bとの間には、原子炉炉心での中性子照
射に伴う各中性子吸収u’+aa。
On the other hand, between the long-life neutron absorbing material 18a at the tip and the next short neutron absorbing material 18b, each neutron absorption u'+aa accompanying neutron irradiation in the reactor core is present.

18b、19の照射成艮艮ざを吸収するための間隙25
が形成され、この間隙25には、ハフニウム(Hf )
ウール等の中性子吸収用金属ウール24が挿入される。
Gap 25 for absorbing irradiation particles 18b and 19
is formed, and in this gap 25, hafnium (Hf)
A neutron absorbing metal wool 24 such as wool is inserted.

この金属ウール24の挿入により、間隙25による中性
子束の盛上りが抑制される一方、制御棒の急激な挿入・
引抜時の際に、短尺中性子吸収U18bの変位移動を抑
制している。
By inserting the metal wool 24, the rise of the neutron flux due to the gap 25 is suppressed, while the rapid insertion of the control rod
During extraction, the displacement movement of the short neutron absorber U18b is suppressed.

Hf’ 1クール等の金属ウールは全体的には低密度充
填であるため、各金属ウールは中性子吸収材の中性子吸
収材の中性子照射成長時には押し潰されて狭くなる。
Since metal wool such as Hf' 1 Cool has a low density packing as a whole, each metal wool is crushed and narrowed during neutron irradiation growth of the neutron absorber.

なお、間隙25に充填される金属ウールとして11 f
ウールの代りにSO3管のようなものとすることができ
、このSO3管等を挿入した場合には ゛この部分に非
吸収材部D2が形成される。しかし、間隙25の挿入方
向長さく幅)は数M程度であり、この程度の長さの場合
、非吸収材部D2による中性子束の盛上りは小さく、し
かしこの非吸収材部D2と中性子吸収棒19の先端部の
非吸収材部D1との間に、長寿命型中性子吸収材18b
が介装しているので、長尺中性子吸収棒19の[34C
頂部において、間隙25にJ:る中性子束の盛上りは確
実に無視でさ゛、第3図(B)に実線C1で示される中
性子分布曲線を有する。符号△およびBは第6図に実線
および破線でそれぞれ示した中性子分布曲線A 33よ
σBである。
In addition, as the metal wool filled in the gap 25, 11 f
Instead of wool, it is possible to use something like an SO3 pipe, and when this SO3 pipe or the like is inserted, a non-absorbing material portion D2 is formed in this part. However, the length and width of the gap 25 in the insertion direction are approximately several meters, and in the case of this length, the increase in neutron flux due to the non-absorbing material portion D2 is small, but the neutron absorption A long-life neutron absorbing material 18b is placed between the tip of the rod 19 and the non-absorbing material portion D1.
is interposed, so that [34C of the long neutron absorption rod 19
At the top, the rise in the neutron flux in the gap 25 is certainly negligible, and has a neutron distribution curve shown by the solid line C1 in FIG. 3(B). The symbols Δ and B are the neutron distribution curves A33 and σB shown in FIG. 6 by solid lines and broken lines, respectively.

ところで、先端の長寿命型短尺の中性子吸収材18aは
挿入方向良さが通常10Cm以上とされ、この中性子吸
収材18 Flに間隙25をおいて隣り合う短尺中性子
吸収材18bに較べて重量がかなり大きい。このため、
制御棒の急激な引抜きによって長尺中性子吸収棒19に
衝撃が及ばないように、先端の中性子吸収材18aはタ
イロッド11の先端突起11aまたは先端構造材12に
係合し、固定される。
By the way, the long-life type short neutron absorbing material 18a at the tip usually has an insertion direction of 10 cm or more, and is considerably heavier than the short neutron absorbing material 18b adjacent to the neutron absorbing material 18 Fl with a gap 25 therebetween. . For this reason,
The neutron absorbing material 18a at the tip engages with the tip protrusion 11a of the tie rod 11 or the tip structural member 12 and is fixed so that no shock is applied to the long neutron absorbing rod 19 due to sudden withdrawal of the control rod.

また、長寿命型中性子吸収材18bは短尺軽重であるた
め、制御棒の急激な挿入や引汰口、Yに移動変化が生じ
ても、長尺中性子吸収棒19の頂部にショックを与える
恐れがない。したがって、短尺の中性子吸収材18bを
ウィング17内で積極的に固定さUる必要はなく、■(
尺の中性子吸収棒19の頂部に当接させることができる
。このため、中性子吸収棒19の頂部の非吸収材部D1
の中性子束力a曲線C1は従来の中性子分布曲線ΔのJ
:うに盛上がらず、抑制された形となる。
Furthermore, since the long-life neutron absorbing material 18b is short, light and heavy, there is a risk of shock to the top of the long neutron absorbing rod 19 even if the control rod is suddenly inserted or there is a movement change in the intake port or Y. do not have. Therefore, there is no need to actively fix the short neutron absorbing material 18b within the wing 17, and
It can be brought into contact with the top of the neutron absorption rod 19 of the length. Therefore, the non-absorbing material portion D1 at the top of the neutron absorbing rod 19
The neutron flux force a curve C1 is J of the conventional neutron distribution curve Δ
: The sea urchin doesn't get excited and has a subdued shape.

この結果、中性子吸収物質21の端部部分の中性子束の
盛上りは、eからfF人わされるように抑制され、端部
部分の局所的な中性子照射iflが抑制される。このた
め、中性子吸収物質21の端部でのB4Cの局所的なス
ウェリングが抑制され、金属被覆管20への局所的な応
力の発生が抑えられる。したがって、長尺型中性子吸収
棒19の叶仝性が向上し、長寿命を達成リ−ることがで
きる。
As a result, the increase in neutron flux at the end portions of the neutron absorbing material 21 is suppressed so as to increase from e to fF, and local neutron irradiation ifl at the end portions is suppressed. Therefore, local swelling of B4C at the end of the neutron absorbing material 21 is suppressed, and the generation of local stress on the metal clad tube 20 is suppressed. Therefore, the durability of the elongated neutron absorption rod 19 is improved, and a long life can be achieved.

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18a〜18Cと長尺の中性子吸
収材19とを組み合し’/ζ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5理解されるJ: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OJを受(プる。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J:び翼端部に長寿命型中竹子吸収材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、制御棒の長ズI命化を図るこ
とができる。
When the long-life neutron absorbing materials 18a to 18C and the elongated neutron absorbing material 19 are combined and the '/ζ hybrid reactor control rod 10 is inserted into the core of the reactor, the control rod 10 will not be irradiated with neutrons. receive. According to experiments, the two-dimensional distribution of neutron flux on the surface of a nuclear reactor control rod subjected to neutron irradiation is
It is represented by a contour diagram showing relative values in the left half of the figure. From this contour map, it is understood that the reactor control rod 10 receives particularly strong neutron radiation at the tips and wing tips of each wing 17. However, in this case, the reactor control rod 10 is provided with long-life bamboo shoot absorbing material 18 at the tips and blade tips of each wing 17, which are exposed to strong neutron irradiation, so that the neutron absorption capacity can be made almost uniform during the neutron irradiation time. , the length of the control rod can be improved.

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+fりでなく、直線的な場合には、第6
図(B)に実線Aで示ずような中性子束の盛上りが生じ
、中性子非吸収材部りに隣接するB4C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8aを局所的に
膨出さけ、破損を生じさせる虞れがある。しかし、本実
施例においては、長寿命型中性子吸収材18bが長尺の
中性子吸収棒19に当接し、しかも各中性子吸収棒19
の中性子照射成長に伴って移動変位可能に収納されてい
るので、第6図に示す隙間オは形成されない。この結果
、中性子束分布曲線01は符号Aで示すような中性子束
の大きな盛上りは抑t、lIされる。このため、長尺中
性子吸収棒19に充填されているB4Cの頂部にお番ノ
る中性子束の盛上りはfで示されるように抑えられ、B
4C頂部への中性子照射量が少なくなる。したがって、
B4Cの局所的なスウェリングが抑制され、金属被覆管
20の局所的応力の発生が緩和され、金属被覆’?’!
 20の舒全性が向上し、制御棒のズI命が増大する。
In general, if the interface between the long-life neutron absorber and the long neutron absorber is straight rather than diagonal, the sixth
A bulge in the neutron flux as shown by the solid line A in Figure (B) occurs, and the fission reaction of boron-10 proceeds in a very limited area of B4C adjacent to the neutron non-absorbing material part, and as a result,
B4C causes swelling and locally bulges the metal cladding tube 8a, which may cause damage. However, in this embodiment, the long-life neutron absorbing material 18b contacts the long neutron absorbing rods 19, and each neutron absorbing rod 19
The gap O shown in FIG. 6 is not formed because it is housed so that it can be moved and displaced in accordance with the growth of neutron irradiation. As a result, in the neutron flux distribution curve 01, a large increase in the neutron flux as indicated by the symbol A is suppressed. Therefore, the bulge of the neutron flux at the top of the B4C filled in the long neutron absorption rod 19 is suppressed as shown by f, and the B
The amount of neutron irradiation to the top of 4C is reduced. therefore,
Local swelling of B4C is suppressed, local stress generation in the metal clad tube 20 is alleviated, and the metal clad '? '!
20's maneuverability is improved, and the life of the control rods is increased.

〔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、短尺の長寿命型中性子吸収材を制御棒の軸方向
に分割し、分割された末端側の長寿命型中性子吸収材を
短尺軽量物として長尺の中性子吸収材に当接して配置し
たので、照射成長に伴う良さの変化を吸収するための長
尺の中性子吸収材と長寿命型中性子吸収材との間に形成
される隙間を取り除くことができ、この結果、長尺の中
性子吸収材に充填された中性子吸収物質のスウエリング
を有効的に押え、このスウェリングにAsづく被覆管の
破損の可能性を低減さけることができるので、長尺の中
性子吸収材の叶仝性や信頼性を向上さ「ることができ、
制ね11棒の長寿命化を確実に図ることができる。
As described above, in the nuclear reactor control rod according to the present invention, the short long-life neutron absorber is divided in the axial direction of the control rod, and the long-life neutron absorber on the divided end side is Since it is placed as a short and lightweight object in contact with the long neutron absorbing material, it is formed between the long neutron absorbing material and the long-life neutron absorbing material to absorb changes in quality due to irradiation growth. The gap can be removed, and as a result, the swelling of the neutron absorbing substance filled in the long neutron absorbing material can be effectively suppressed, and the possibility of damage to the cladding tube due to As caused by this swelling can be reduced and avoided. Therefore, the performance and reliability of long neutron absorbing materials can be improved.
It is possible to reliably extend the life of the restraining rod 11.

【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
部分的縦断面図、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ず部分図、第3図(
A>および(B)は本発明に係る原子炉用制011棒に
おける各中性子吸収材の配置関係おJ:び中性子束分布
の関係をそれぞれ示1図、第4図は従来の原子炉用制御
棒を示寸斜祝図、第5図は第4図のv−v線に沿う平断
面図、fj6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J3 
、及び中性子束分布の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・・・先端構造材、16・・・シース、17・・・ウ
ィング、18a、18b、18c・・・長17Q型中性
子吸取材、19・・・長尺の中性子吸収棒、19a・〜
19f・・・中性子吸収棒、20・・・金属被覆管、2
1・・・中性子吸収物質、22・・・金属ウール、23
・・・プラグ、Dl、D2・・・非吸収材部。 出願人代理人   波 多 野   久蔓 1 図 羊 2 図 イ立1l− CB> 名3 図 弔4I21 某 5 図 イ立511 CB) 第 6 図
FIG. 1 is a partial longitudinal sectional view showing an embodiment of a nuclear reactor control rod according to the present invention, and FIG. 2 shows a long neutron absorption rod and a long life that are incorporated into the wing of the nuclear reactor control rod. Figure 3 is a partial view (not shown in an enlarged manner) of the arrangement relationship with the type neutron absorber (
A> and (B) respectively show the arrangement relationship of each neutron absorbing material and the relationship of neutron flux distribution in the nuclear reactor control rod according to the present invention. Figure 5 is a cross-sectional view along the v-v line in Figure 4, and Figures (A) and (B) are each neutron absorption diagram incorporated into a conventional control rod for a nuclear reactor. Material placement relationship J3
, and neutron flux distribution, respectively. 10... Nuclear reactor control rod, 11... Tie rod, 1
2... Tip structure material, 16... Sheath, 17... Wing, 18a, 18b, 18c... Long 17Q type neutron absorption material, 19... Long neutron absorption rod, 19a...
19f...neutron absorption rod, 20...metal clad tube, 2
1... Neutron absorbing substance, 22... Metal wool, 23
... Plug, Dl, D2... Non-absorbing material part. Applicant's agent Hisatsuri Hatano 1 Figure 2 Figure 11- CB> Name 3 Figure 4 I21 Certain 5 Figure 511 CB) Figure 6

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、前記短尺の長寿命型中性子吸収材は
制御棒の軸方向に分割され、分割された末端側の長寿命
型中性子吸収材は短尺軽量物とされて前記長尺の中性子
吸収材に当接して配置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材は制御棒の軸方向に微小間隙
をおいて2分割され、分割された先端の長寿命型中性子
吸収材はタイロッドおよび先端構造材に係合させた特許
請求の範囲第1項に記載の原子炉用制御棒。 3、微小間隙は、長尺の中性子吸収材の中性子照射成長
長さを吸収するため、数mm程度の幅である特許請求の
範囲第1項に記載の原子炉用制御棒。 4、微小間隙にはハフニウムウール等の金属ウールが介
装された特許請求の範囲第1項に記載の原子炉用制御棒
。 5、分割された末端側の長寿命型中性子吸収材は挿入方
向の長さが1〜3cm程度である特許請求の範囲第1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 short long-life neutron absorbing material is divided in the axial direction of the control rod, and the long-life neutron absorbing material at the end of the division is made short and lightweight and corresponds to the long neutron absorbing material. A control rod for a nuclear reactor characterized by being arranged in contact with each other. 2. The long-life neutron absorber is divided into two parts with a small gap in the axial direction of the control rod, and the long-life neutron absorber at the tip of the divided part is engaged with the tie rod and the tip structure member. The control rod for a nuclear reactor according to item 1. 3. The control rod for a nuclear reactor according to claim 1, wherein the minute gap has a width of about several mm in order to absorb the neutron irradiation growth length of the long neutron absorbing material. 4. The control rod for a nuclear reactor according to claim 1, wherein a metal wool such as hafnium wool is interposed in the minute gap. 5. The control rod for a nuclear reactor according to claim 1, wherein the long-life neutron absorber on the divided end side has a length of about 1 to 3 cm in the insertion direction.
JP61029005A 1986-02-14 1986-02-14 Control rod for nuclear reactor Expired - Lifetime JPH0816716B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61029005A JPH0816716B2 (en) 1986-02-14 1986-02-14 Control rod for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61029005A JPH0816716B2 (en) 1986-02-14 1986-02-14 Control rod for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS62187284A true JPS62187284A (en) 1987-08-15
JPH0816716B2 JPH0816716B2 (en) 1996-02-21

Family

ID=12264285

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61029005A Expired - Lifetime JPH0816716B2 (en) 1986-02-14 1986-02-14 Control rod for nuclear reactor

Country Status (1)

Country Link
JP (1) JPH0816716B2 (en)

Cited By (1)

* 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

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60220893A (en) * 1984-04-18 1985-11-05 株式会社日立製作所 Control rod for nuclear reactor
JPS6129792A (en) * 1984-07-20 1986-02-10 株式会社東芝 Control rod for nuclear reactor
JPS61189488A (en) * 1985-02-18 1986-08-23 株式会社東芝 Control rod for nuclear reactor

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60220893A (en) * 1984-04-18 1985-11-05 株式会社日立製作所 Control rod for nuclear reactor
JPS6129792A (en) * 1984-07-20 1986-02-10 株式会社東芝 Control rod for nuclear reactor
JPS61189488A (en) * 1985-02-18 1986-08-23 株式会社東芝 Control rod for nuclear reactor

Cited By (1)

* 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

Also Published As

Publication number Publication date
JPH0816716B2 (en) 1996-02-21

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