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JPH026037B2 - - Google Patents
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JPH026037B2 - - Google Patents

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Publication number
JPH026037B2
JPH026037B2 JP56055586A JP5558681A JPH026037B2 JP H026037 B2 JPH026037 B2 JP H026037B2 JP 56055586 A JP56055586 A JP 56055586A JP 5558681 A JP5558681 A JP 5558681A JP H026037 B2 JPH026037 B2 JP H026037B2
Authority
JP
Japan
Prior art keywords
rod
neutron
life
long
plenum
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
JP56055586A
Other languages
Japanese (ja)
Other versions
JPS57171292A (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
Nippon Genshiryoku Jigyo KK
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
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 Genshiryoku Jigyo KK filed Critical Toshiba Corp
Priority to JP56055586A priority Critical patent/JPS57171292A/en
Publication of JPS57171292A publication Critical patent/JPS57171292A/en
Publication of JPH026037B2 publication Critical patent/JPH026037B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は沸騰水型原子炉用制御棒に係り、特に
重量の増加を招かずに長寿命化を図つた沸騰水型
原子炉用制御棒に関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a control rod for a boiling water type nuclear reactor, and in particular to a control rod for a boiling water type nuclear reactor, which has a long life without increasing the weight. Regarding control rods for nuclear reactors.

(従来の技術) 従来の沸騰水型原子炉用制御棒は、十字状断面
を有するタイロツドの各突出脚に、細長いU字状
断面を有するシースの開口部をそれぞれ取り付け
て十字状のウイングを形成し、各ウイング内の垂
直方向に互いに平行に多数の中性子吸収棒を装填
して構成されている。
(Prior art) A conventional control rod for a boiling water nuclear reactor has a cross-shaped wing formed by attaching an opening in a sheath having an elongated U-shaped cross section to each protruding leg of a tie rod having a cross-shaped cross section. It is constructed by loading a large number of neutron absorption rods vertically and parallel to each other within each wing.

而して、中性子吸収棒は被覆管内に中性子吸収
材、例えばB4Cの粉末またはペレツトを充填して
成る。
The neutron absorbing rod is constructed by filling a cladding tube with a neutron absorbing material, such as B 4 C powder or pellets.

この中性子吸収棒を装填した制御棒を原子炉炉
心に挿入して使用すると、B4C粉末、ペレツト等
は中性子を吸収して損耗し中性子吸収能力を徐々
に失い、同時に核反応によつてHeガスや三重水
素(3T2)ガス等を発生する。ここでHeガスは
B4C中の質量数10のボロン(B―10)が中性子の
照射を受け、いわゆる(n,α)反応によつて生
じるものであり、3T2ガスは、上記(n,α)反
応によつて生じた7Liと高速中性子との核反応に
よつて生成するものである。またB4Cで形成した
中性子吸収棒を寿命終了までに使用したときの
3T2原子の発生量はHe原子の発生量の約0.03%で
あり、発生ガスの大部分はHeガスである。
When a control rod loaded with this neutron absorption rod is inserted into a nuclear reactor core and used, B 4 C powder, pellets, etc. absorb neutrons and are worn out, gradually losing their neutron absorption ability. Generates gas, tritium ( 3 T 2 ) gas, etc. Here He gas is
Boron (B-10) with a mass number of 10 in B 4 C is irradiated with neutrons and is generated by the so-called (n, α) reaction, and 3 T 2 gas is generated by the above (n, α) reaction. It is produced by a nuclear reaction between 7 Li produced by neutrons and fast neutrons. In addition, when a neutron absorbing rod made of B 4 C is used until the end of its life,
The amount of 3T2 atoms generated is approximately 0.03% of the amount of He atoms generated, and most of the gas generated is He gas.

したがつて中性子照射時間と共に中性子吸収能
力は低下し、被覆管内のガス圧は上昇する。中性
子吸収能力が予め定めた値となるまでに必要な中
性子照射時間を核的寿命、被覆管内圧が許容値に
達するまでの中性子照射時間を機械的寿命と呼ん
でいる。最近の研究によると機械的寿命の方が核
的寿命よりも短く、中性子吸収棒の寿命は機械的
寿命により定まつている。
Therefore, as the neutron irradiation time increases, the neutron absorption capacity decreases and the gas pressure within the cladding tube increases. The neutron irradiation time required until the neutron absorption capacity reaches a predetermined value is called the nuclear life, and the neutron irradiation time required until the cladding internal pressure reaches an allowable value is called the mechanical life. According to recent research, the mechanical lifetime is shorter than the nuclear lifetime, and the lifetime of a neutron absorbing rod is determined by the mechanical lifetime.

これに対し、Hfメタル、Eu2O3、Ag―In―Cd
等の中性子吸収材は、中性子吸収によりガスを発
生せず、またHf,Eu,Ag,In,Cd等は、中性
子を数回に亘つて吸収した場合においても中性子
吸収断面積の低下が少ない複数の同位体等を形成
したり、中性子吸収性を有する原子に変換された
りする。そのため、長期間に亘つて中性子吸収を
行なうことが可能であり、いわゆる長寿命型中性
子吸収材と呼ばれ、長寿命の中性子吸収棒を構成
するために使用されている。
On the other hand, Hf metal, Eu 2 O 3 , Ag―In―Cd
Neutron absorbing materials such as Hf, Eu, Ag, In, Cd, etc. do not generate gas by absorbing neutrons, and Hf, Eu, Ag, In, Cd, etc. It forms isotopes, etc., or is converted into atoms that have neutron absorbing properties. Therefore, it is possible to absorb neutrons for a long period of time, and is called a long-life neutron absorbing material, and is used to construct a long-life neutron absorption rod.

(発明が解決しようとする課題) しかしながらHfメタル、Eu2O3、Ag―In―Cd
等の長寿命型中性子吸収材は一般に密度が大きく
かつ高価であるため、多量に使用すると制御棒の
重量が過大になり、しかも高価となる。この重量
が大幅に増加した制御棒を使用する場合には、制
御棒駆動機構の構造強度をより強化する設計変更
が必要であり、容易に既設の原子炉設備に転用し
得ない実用上の問題点があつた。したがつて転用
性をもたせるためには長寿命型中性子吸収材の使
用量を最少限に抑え、制御棒全体の重量増加を招
かない構造が望まれていた。
(Problem to be solved by the invention) However, Hf metal, Eu 2 O 3 , Ag-In-Cd
Long-life neutron absorbers such as neutron absorbers generally have a high density and are expensive, so if they are used in large quantities, the weight of the control rod becomes excessive and it becomes expensive. When using control rods with significantly increased weight, it is necessary to change the design to further strengthen the structural strength of the control rod drive mechanism, which is a practical problem that cannot be easily transferred to existing nuclear reactor equipment. The point was hot. Therefore, in order to have versatility, it has been desired to have a structure that minimizes the amount of long-life neutron absorbing material used and does not increase the weight of the control rod as a whole.

本発明は上記の事情を考慮してなされたもの
で、高価でしかも重い長寿命型中性子吸収材の使
用量を最少限とし、かつ長寿命化を図つた沸騰水
型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 circumstances, and provides a control rod for a boiling water reactor that minimizes the amount of expensive and heavy long-life neutron absorbing material used and has a long life. The purpose is to

〔発明の構成〕[Structure of the invention]

(課題を解決するための手段) 上記目的を達成するため本発明は、十字状断面
を有するタイロツドの各突出脚に、細長いU字状
断面を有するシースの開口部をそれぞれ取り付け
てウイングを構成し、ウイング内の幅方向に多数
の中性子吸収棒を装填して成る沸騰水型原子炉用
制御棒において、上端部にプレナムを形成し中性
子吸収材としてB4C粉末を充填したプレナム付中
性子吸収棒を、上記タイロツド近傍に配設する一
方、中性子吸収によりガスを発生しないハフニウ
ム材で形成した長寿命型中性子吸収棒を上記ウイ
ング側縁近傍に配設するとともに、上記タイロツ
ド近傍とウイング側縁近傍との中間部には、上記
プレナム付中性子吸収棒と、上端近傍にハフニウ
ム材で形成した長寿命型中性子吸収材を充填し上
端近傍以下にB4C粉末を充填して成る混成型中性
子吸収棒とを交互に配置したことを特徴とする。
(Means for Solving the Problems) In order to achieve the above object, the present invention configures a wing by attaching an opening of a sheath having an elongated U-shaped cross section to each protruding leg of a tie rod having a cross-like cross section. , a control rod for a boiling water reactor consisting of a large number of neutron absorption rods loaded in the width direction within the wing, with a plenum formed at the upper end and filled with B 4 C powder as a neutron absorption material. is arranged near the tie rod, while a long-life neutron absorption rod made of hafnium material, which does not generate gas by absorbing neutrons, is arranged near the wing side edge. In the middle part, there is a hybrid neutron absorbing rod consisting of the neutron absorbing rod with a plenum, a long-life neutron absorbing material made of hafnium material near the upper end, and B 4 C powder below the upper end. It is characterized by the fact that they are arranged alternately.

(作用) 上記構成に係る沸騰水型原子炉用制御棒によれ
ば、強い中性子照射を受けるウイング側縁および
上端のみに長寿命型の中性子吸収棒を配置してい
るため、制御棒全体としての寿命が延伸されると
ともに、制御棒の大幅な重量増加が抑えられ、既
設の原子炉設備への転用も容易となり、また製造
コストも低減される。
(Function) According to the control rod for a boiling water reactor having the above configuration, long-life neutron absorption rods are arranged only on the side edges and upper ends of the wings that are exposed to strong neutron irradiation, so that the control rod as a whole In addition to extending the life of the control rods, a significant increase in the weight of the control rods is suppressed, making it easier to use them in existing nuclear reactor equipment, and reducing manufacturing costs.

一方、タイロツドの近傍にはプレナムを有し
B4C粉末を充填したプレナム付中性子吸収棒を配
置しているため、タイロツドに最も近い燃料棒
の、制御棒引抜時の出力上昇率が抑制され燃料の
健全性を確保することができる。
On the other hand, there is a plenum near the tie rod.
Because neutron absorption rods with plenums filled with B 4 C powder are installed, the output increase rate of the fuel rod closest to the tie rod when the control rod is withdrawn is suppressed, ensuring the integrity of the fuel.

さらに、プレナム付中性子吸収棒には、中性子
照射の最も強い部位に大きなプレナムを設けてい
るので、核反応で生成したHeガス、3T2ガス等に
よる被覆管内圧の上昇を抑制することができる。
さらに、中性子吸収棒上端にB4Cが存在する時、
核反応および化学反応物と被覆管との反応および
内圧の上昇により、吸収棒の機械的寿命が低下す
るおそれがあるが、本発明においてはB4Cを充填
した中性子吸収棒上端にプレナムを設けてあるの
でそのおそれはない。
Furthermore, the neutron absorption rod with a plenum has a large plenum installed in the area where neutron irradiation is strongest, so it is possible to suppress the increase in the internal pressure of the cladding tube due to He gas, 3 T 2 gas, etc. generated in the nuclear reaction. .
Furthermore, when B 4 C exists at the top of the neutron absorption rod,
There is a risk that the mechanical life of the absorption rod will be reduced due to nuclear reactions, reactions between chemical reactants and the cladding, and increases in internal pressure. However, in the present invention, a plenum is provided at the upper end of the neutron absorption rod filled with B4C . There is no risk of that happening.

(実施例) 次に本発明の一実施例について添付図面を参照
して説明する。添付図面は本発明に係る沸騰水型
原子炉用制御棒の一実施例の要部を示す断面図で
ある。
(Example) Next, an example of the present invention will be described with reference to the accompanying drawings. The accompanying drawing is a sectional view showing a main part of an embodiment of a control rod for a boiling water reactor according to the present invention.

すなわち本実施例に係る沸騰水型原子炉用制御
棒は、十字状断面を有するタイロツド1の各突出
脚に細長いU字状断面を有するシースの開口部を
それぞれ取り付けてウイング2を構成し、ウイン
グ2内の幅方向に多数の中性子吸収棒を装填して
成る沸騰水型原子炉用制御棒において、上端部に
プレナム4aを形成し中性子吸収材としてB4C粉
末5bを充填したプレナム付中性子吸収棒4を、
上記タイロツド1近傍に配設する一方、中性子吸
収によりガスを発生しないハフニウム材で形成し
た長寿命型中性子吸収棒3を上記ウイング2の側
縁近傍に配設するとともに、上記タイロツド1の
近傍とウイング2の側縁近傍との中間部には、上
記プレナム付中性子吸収棒4と、上端近傍にハフ
ニウム材で形成した長寿命型中性子吸収材5aを
充填し上端近傍以下にB4C粉末5bを充填して成
る混成型中性子吸収棒5とを交互に配置して構成
される。
That is, in the control rod for a boiling water reactor according to this embodiment, a wing 2 is constructed by attaching an opening of a sheath having an elongated U-shaped cross section to each protruding leg of a tie rod 1 having a cross-shaped cross section. A control rod for a boiling water reactor comprising a large number of neutron absorbing rods loaded in the width direction within the plenum 4a at the upper end and filled with B 4 C powder 5b as a neutron absorbing material. stick 4,
A long-life neutron absorbing rod 3 made of hafnium material that does not generate gas by absorbing neutrons is arranged near the side edge of the wing 2. 2, the neutron absorbing rod 4 with a plenum and a long-life neutron absorbing material 5a made of hafnium material are filled near the upper end, and B 4 C powder 5b is filled below the upper end. The hybrid neutron absorption rods 5 are arranged alternately.

より具体的に構成を説明すると、ウイング2の
側縁近傍2cm位の幅にはウイング2全長に亘る2
本の長寿命型中性子吸収棒3が配置され、タイロ
ツド1近傍の2cm位の幅には、上端に10〜30cm程
度の長さのプレナム4aを有するプレナム付中性
子吸収棒4が配置されている。またウイング2内
のそれら中性子吸収棒3,4の間には、上端部に
長寿命型中性子吸収材5aを30cm程度の長さにわ
たり配置したものであり、かつ上端部以外の部分
に通常寿命型中性子吸収材であるB4C粉末5bを
充填して成る混成型中性子吸収棒5と、タイロツ
ド5近傍に配設した中性子吸収棒と構成を等しく
したプレナム付中性子吸収棒4とが交互に配置さ
れている。
To explain the configuration more specifically, there is a 2 cm width near the side edge of the wing 2 that spans the entire length of the wing 2.
A long-life neutron absorption rod 3 is arranged, and a plenum-equipped neutron absorption rod 4 having a plenum 4a with a length of about 10 to 30 cm at the upper end is arranged in a width of about 2 cm near the tie rod 1. Furthermore, between the neutron absorbing rods 3 and 4 in the wing 2, a long-life neutron absorbing material 5a is arranged at the upper end over a length of about 30 cm, and a normal-life neutron absorbing material 5a is arranged at the upper end over a length of about 30 cm. Hybrid neutron absorbing rods 5 filled with B 4 C powder 5b, which is a neutron absorbing material, and neutron absorbing rods 4 with plenums having the same configuration as the neutron absorbing rods arranged near the tie rods 5 are arranged alternately. ing.

ここで長寿命型中性子吸収棒3および長寿命型
中性子吸収材5aを構成するハフニウム材として
は、被覆管に装填されることなく、むき出し状態
のハフニウム棒を使用している。
Here, as the hafnium material constituting the long-life neutron absorption rod 3 and the long-life neutron absorption material 5a, an exposed hafnium rod is used without being loaded into a cladding tube.

なお長寿命を有する中性子吸収材としてAg―
In―Cd合金やEu2O3粉末を用いる考えもあるが、
Agは放射化して炉水中に溶け込み、炉水の放射
線レベルを上昇させるおそれがある。そのため使
用する場合には被覆管内に収容して密封保持する
必要がある。一方、ユーロピウムは希土類の中で
も特に高価な材料であるため、コスト上難点が多
い。
Furthermore, Ag- is used as a neutron absorbing material with long life.
There is also the idea of using In-Cd alloy or Eu 2 O 3 powder, but
Ag becomes radioactive and dissolves into the reactor water, potentially increasing the radiation level of the reactor water. Therefore, when used, it is necessary to house it in a cladding tube and keep it sealed. On the other hand, europium is a particularly expensive material among rare earths, so it has many disadvantages in terms of cost.

本実施例に係る沸騰水型原子炉用制御棒によれ
ば、強い中性子照射を受けるウイング2の側縁お
よび上端のみに長寿命型の中性子吸収材を配置し
ているため、制御棒全体としての寿命が大幅に延
伸されるともとに、制御棒の大幅な重量増加が回
避され、既設の原子炉設備への転用も容易とな
る。
According to the boiling water reactor control rod according to this embodiment, long-life neutron absorbing materials are placed only on the side edges and upper ends of the wing 2, which are exposed to strong neutron irradiation, so that the control rod as a whole Not only will the lifespan be significantly extended, but a significant increase in the weight of the control rods will be avoided, and it will be easier to convert it into existing nuclear reactor equipment.

また、高価な長寿命型中性子吸収材の使用量を
必要最少量に抑えているため、制御棒の製造コス
トの上昇も少ない。
Furthermore, since the amount of expensive long-life neutron absorbing material used is kept to the minimum necessary amount, the manufacturing cost of the control rods does not increase much.

一方、タイロツド1の近傍にはプレナム4aを
有し、通常のB4C粉末を充填したプレナム付中性
子吸収棒4を配置しているため、タイロツド1に
最も近い燃料棒における、制御棒引抜時の出力上
昇率が抑制され、燃料の健全性を確保することが
できるる。
On the other hand, a plenum 4a is provided near the tie rod 1, and a neutron absorbing rod 4 with a plenum filled with normal B 4 C powder is arranged, so that when the control rod is withdrawn, the fuel rod closest to the tie rod 1 is The output increase rate is suppressed and the soundness of the fuel can be ensured.

また制御棒上端部においては、B4Cより寿命が
長い反面、反応度が低いハフニウム材が配設され
ているため、上端部において部分的に反応度価値
が低下するが、制御棒全体からみた場合には無視
できる程度である。
In addition, at the upper end of the control rod, hafnium material, which has a longer life than B 4 C but has a lower reactivity, is installed, so the reactivity value partially decreases at the upper end, but from the perspective of the entire control rod. In some cases, it is negligible.

しかし上端部の反応度が低下している分だけ制
御棒引抜時の隣接燃料集合体の出力上昇幅を減じ
ることができるという効果もある。
However, there is also the effect that the amount of increase in the output of the adjacent fuel assembly when the control rod is withdrawn can be reduced by the amount that the reactivity of the upper end is reduced.

さらに、通常寿命型中性子吸収材としてB4Cを
充填したプレナム付中性子吸収棒4には、中性子
照射の最も強い部位に大きなプレナム4aを設け
てあるので、核反応で生成したHeガス、3T2ガス
等による被覆管内圧の上昇を抑制することができ
る。すなわち中性子吸収棒上端にB4Cが存在する
従来の制御棒においては、核反応および化学反応
物と被覆管との反応および内圧の上昇により、吸
収棒の機械的寿命が短期間で低下するおそれがあ
るが、本実施例においてはB4C粉末5bを充填し
た中性子吸収棒上端に大きなプレナム4aを設け
てあるので発生ガスはプレナム4a内に逐次に貯
留され、運転サイクル末期においてもガス圧が異
常に高くなるおそれは少ない。
Furthermore, the neutron absorbing rod 4 with a plenum filled with B 4 C as a normal-life neutron absorbing material has a large plenum 4a in the area where neutron irradiation is strongest, so He gas generated by nuclear reaction, 3 T 2) It is possible to suppress the increase in the internal pressure of the cladding tube due to gas, etc. In other words, in conventional control rods in which B 4 C is present at the upper end of the neutron absorption rod, the mechanical life of the absorption rod may be shortened in a short period of time due to nuclear reactions, reactions between chemical reactants and the cladding, and increases in internal pressure. However, in this embodiment, a large plenum 4a is provided at the upper end of the neutron absorption rod filled with B 4 C powder 5b, so the generated gas is stored in the plenum 4a one after another, and the gas pressure is maintained even at the end of the operation cycle. There is little chance of it becoming abnormally high.

本発明は上記実施例に限定されない、例えばプ
レナム付中性子吸収棒4において、プレナム4a
内に中空体、メタルウール等の部材を配置しても
よい。それらの部材は核反応、化学反応生成物を
吸着するものとすることが望ましい。
The present invention is not limited to the above-mentioned embodiments. For example, in the neutron absorption rod 4 with a plenum, the plenum 4a
A member such as a hollow body or metal wool may be placed inside. It is desirable that these members adsorb nuclear reaction and chemical reaction products.

また、水分や酸素を吸着除去する活性金属であ
るゲツタをプレナム内に配置してもよい。また、
混成型中性子吸収棒5において、長寿命型中性子
吸収材5aと、通常寿命中性子吸収材としての
B4C粉末5bとの間に、メタルウール等のウール
状部材5cを介在させてもよい。すなわち長寿命
型中性子吸収材5aを挿入する時、その下端にウ
ール状部材5cを当接して、長寿命型中性子吸収
材5aの挿入と同時にウール状部材5cを押し込
むようにすることにり、被覆管内面に固着してい
たB4C粉末5bはウール状部材5cとともに下方
に押し下げられ、またウール状部材5cは下方の
B4C粉末5bの上方への移動を防止するので、長
寿命型中性子吸収材5aと被覆管内面との間に
B4C粉末5bが入り込むことはない。そのため
B4C粉末5bを介して被覆管に押圧力が作用して
局所的応力を生じるおそれはない。また、長寿命
型中性子吸収材5a挿入時において、その下端角
部が被覆管内面に引つ掛つて傷を付けたり、かじ
り等を生じるおそれがない。
Further, a getter, which is an active metal that adsorbs and removes moisture and oxygen, may be placed in the plenum. Also,
In the hybrid neutron absorption rod 5, a long-life neutron absorption material 5a and a normal-life neutron absorption material are used.
A wool-like member 5c such as metal wool may be interposed between the B 4 C powder 5b and the B 4 C powder 5b. That is, when inserting the long-life neutron absorber 5a, the wool-like member 5c is brought into contact with the lower end of the long-life neutron absorber 5a, and the wool-like member 5c is pushed in at the same time as the long-life neutron absorber 5a is inserted. The B 4 C powder 5b that had adhered to the inner surface of the tube is pushed down together with the wool-like member 5c, and the wool-like member 5c is pushed downward.
B 4 C powder 5b is prevented from moving upward, so there is a gap between the long-life neutron absorber 5a and the inner surface of the cladding tube.
B 4 C powder 5b does not enter. Therefore
There is no possibility that a pressing force will act on the cladding tube through the B 4 C powder 5b and cause local stress. Further, when the long-life neutron absorbing material 5a is inserted, there is no risk that the lower end corner portion of the material will catch on the inner surface of the cladding tube and cause damage or galling.

また、プレナム4aの長さは、制御棒の反応度
価値が低下しない範囲でかつ中性子照射の著しく
強い範囲を避ける領域、すなわち制御棒上端から
10〜30cmまでの領域に形成することが望ましい。
In addition, the length of the plenum 4a is determined within a range that does not reduce the reactivity value of the control rod and avoids a region where neutron irradiation is extremely strong, that is, from the upper end of the control rod.
It is desirable to form in an area of 10 to 30 cm.

さらに、長寿命型中性子吸収材5aの長さは制
御棒が強い中性子照射を受ける部位の長さ、すな
わち制御棒の上端から30cm〜ウイング有効長の約
1/4に設定する。
Furthermore, the length of the long-life neutron absorbing material 5a is set to the length of the part of the control rod that receives strong neutron irradiation, that is, from 30 cm from the upper end of the control rod to about 1/4 of the effective length of the wing.

また、ウイング2側縁近傍にウイングの全有効
長に亘る長さの長寿命型中性子吸収材5aを必ず
しも配置する必要はなく、全有効長の上半分のみ
に配置するようにしてもよい。
Further, it is not necessary to arrange the long-life neutron absorbing material 5a over the entire effective length of the wing near the side edge of the wing 2, and it may be arranged only over the upper half of the entire effective length.

〔発明の効果〕〔Effect of the invention〕

以上説明の通り本発明に係る沸騰水型原子炉用
制御棒によれば、強い中性子照射を受けるウイン
グ側縁および上端のみに長寿命型の中性子吸収棒
を配置しているため、制御棒全体としての寿命が
延伸されるとともに、制御棒の大幅な重量増加が
抑えられ、既設の原子炉設備への転用も容易とな
り、また製造コストも低減される。
As explained above, according to the control rod for a boiling water reactor according to the present invention, long-life neutron absorption rods are arranged only on the side edges and upper ends of the wings, which are exposed to strong neutron irradiation, so that the control rod as a whole The lifespan of the control rods will be extended, a significant increase in the weight of the control rods will be suppressed, it will be easier to use the control rods in existing reactor equipment, and manufacturing costs will be reduced.

一方、タイロツドの近傍には、プレナムを有し
B4C粉末を充填したプレナム付中性子吸収棒を配
置しているため、タイロツドに最も近い燃料棒
の、制御棒引抜時の出力上昇率が抑制され燃料の
健全性を確保することができる。
On the other hand, there is a plenum near the tie rod.
Because neutron absorption rods with plenums filled with B 4 C powder are installed, the output increase rate of the fuel rod closest to the tie rod when the control rod is withdrawn is suppressed, ensuring the integrity of the fuel.

さらに、プレナム付中性子吸収棒には、中性子
照射の最も強い部位に大きなプレナムを設けてい
るので、核反応で生成したHeガス、3T2ガス等に
よる被覆管内圧の上昇を抑制することができる。
さらに、中性子吸収棒上端にB4Cが存在する時、
核反応および化学反応物と被覆管との反応および
内圧の上昇により、吸収棒の機械的寿命が低下す
るおそれがあるが、本発明においてはB4Cを充填
した中性子吸収棒上端にプレナムを設けてあるの
でそのおそれはない。
Furthermore, the neutron absorption rod with a plenum has a large plenum installed in the area where neutron irradiation is strongest, so it is possible to suppress the increase in the internal pressure of the cladding tube due to He gas, 3 T 2 gas, etc. generated in the nuclear reaction. .
Furthermore, when B 4 C exists at the top of the neutron absorption rod,
There is a risk that the mechanical life of the absorption rod will be reduced due to nuclear reactions, reactions between chemical reactants and the cladding, and increases in internal pressure. However, in the present invention, a plenum is provided at the upper end of the neutron absorption rod filled with B4C . There is no risk of that happening.

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

図は本発明の一実施例の要部を示す断面図であ
る。 1…タイロツド、2…ウイング、3…長寿命型
中性子吸収棒、4…プレナム付中性子吸収棒、4
a…プレナム、5…混成型中性子吸収棒、5a…
長寿命型中性子吸収材、5b…B4C粉末、5c…
ウール状部材。
The figure is a sectional view showing a main part of an embodiment of the present invention. 1... Tie rod, 2... Wing, 3... Long-life neutron absorption rod, 4... Neutron absorption rod with plenum, 4
a... Plenum, 5... Hybrid neutron absorption rod, 5a...
Long-life neutron absorber, 5b...B 4 C powder, 5c...
Wool-like material.

Claims (1)

【特許請求の範囲】[Claims] 1 十字状断面を有するタイロツドの各突出脚
に、細長いU字状断面を有するシースの開口部を
それぞれ取り付けてウイングを構成し、ウイング
内の幅方向に多数の中性子吸収棒を装填して成る
沸騰水型原子炉用制御棒において、上端部にプレ
ナムを形成し中性子吸収材としてB4C粉末を充填
したプレナム付中性子吸収棒を、上記タイロツド
近傍に配設する一方、中性子吸収によりガスを発
生しないハフニウム材で形成した長寿命型中性子
吸収棒を上記ウイング側縁近傍に配設するととも
に、上記タイロツド近傍とウイング側縁近傍との
中間部には、上記プレナム付中性子吸収棒と、上
端近傍にハフニウム材で形成した長寿命型中性子
吸収材を充填し上端近傍以下にB4C粉末を充填し
て成る混成型中性子吸収棒とを交互に配置したこ
とを特徴とする沸騰水型原子炉用制御棒。
1 A boiler consisting of a wing formed by attaching an opening of a sheath having an elongated U-shaped cross section to each protruding leg of a tie rod having a cross-shaped cross section, and loading a large number of neutron absorption rods in the width direction within the wing. In control rods for water reactors, a neutron absorption rod with a plenum formed at the upper end and filled with B 4 C powder as a neutron absorbing material is installed near the tie rod, but does not generate gas by absorbing neutrons. A long-life neutron absorption rod made of hafnium material is arranged near the side edge of the wing, and the neutron absorption rod with plenum is placed between the tie rod and the wing side edge, and the neutron absorption rod is made of hafnium near the upper end. A control rod for a boiling water reactor, characterized in that hybrid neutron absorbing rods filled with a long-life neutron absorbing material made of a neutron absorbing material made of carbonaceous material and a hybrid neutron absorbing rod filled with B 4 C powder below the upper end are arranged alternately. .
JP56055586A 1981-04-15 1981-04-15 Control rod of bwr type reactor Granted JPS57171292A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56055586A JPS57171292A (en) 1981-04-15 1981-04-15 Control rod of bwr type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56055586A JPS57171292A (en) 1981-04-15 1981-04-15 Control rod of bwr type reactor

Publications (2)

Publication Number Publication Date
JPS57171292A JPS57171292A (en) 1982-10-21
JPH026037B2 true JPH026037B2 (en) 1990-02-07

Family

ID=13002841

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56055586A Granted JPS57171292A (en) 1981-04-15 1981-04-15 Control rod of bwr type reactor

Country Status (1)

Country Link
JP (1) JPS57171292A (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SE444743B (en) * 1984-09-03 1986-04-28 Asea Atom Ab Nuclear reactor control rod
JP2009270998A (en) * 2008-05-09 2009-11-19 Hitachi-Ge Nuclear Energy Ltd Control rod
AT508801B1 (en) 2009-10-07 2011-09-15 Ge Jenbacher Gmbh & Co Ohg BRENNKRAFTMASCHINENZÜNDVORRICHTUNG
JP2012202877A (en) * 2011-03-25 2012-10-22 Hitachi-Ge Nuclear Energy Ltd Control rod for boiling-water reactor and manufacturing method thereof

Also Published As

Publication number Publication date
JPS57171292A (en) 1982-10-21

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