JPS61180187A - Control rod for nuclear reactor - Google Patents

Control rod for nuclear reactor

Info

Publication number
JPS61180187A
JPS61180187A JP60019858A JP1985885A JPS61180187A JP S61180187 A JPS61180187 A JP S61180187A JP 60019858 A JP60019858 A JP 60019858A JP 1985885 A JP1985885 A JP 1985885A JP S61180187 A JPS61180187 A JP S61180187A
Authority
JP
Japan
Prior art keywords
control rod
nuclear reactor
wing
metal plate
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
JP60019858A
Other languages
Japanese (ja)
Inventor
精 植田
桜田 光一
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 JP60019858A priority Critical patent/JPS61180187A/en
Publication of JPS61180187A publication Critical patent/JPS61180187A/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挿抜され
る原子炉用制御棒に係り、特に金属製中性子吸収材を用
いた長寿命型の原子炉用制御棒に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a control rod for a nuclear reactor that is inserted into and removed from the core of a nuclear reactor such as a boiling water reactor, and particularly relates to a control rod for a nuclear reactor that is inserted into and removed from the core of a nuclear reactor such as a boiling water reactor. Concerning long-life nuclear reactor control rods.

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

一般にこの種の原子炉用制御棒は沸騰水型原子炉などの
炉心部に挿抜されて、原子炉の運転を制御するようにな
っている。従来の原子炉用制御棒は、第4図(A)およ
び(B)に示すように、十字状横断面を有するタイロッ
ド1の各突脚に、深・いU字状断面のシース2を取付け
てウィング3を構成し、各ウィング3内に複数の中性子
吸収棒4が列状に配設される。中性子吸収棒4はステン
レス鋼製被覆管5内にボOンカーパイド(84C)の中
性子吸収材6を充填したものである。なお、符号7はハ
ンドル8を取付けた先端構造材であり、この先端構造材
7にはi、lJ御棒の挿入を案内するガイドローラ9a
が取付()られている。符号9bは冷却材の通水孔であ
る。
Generally, this type of nuclear reactor control rod is inserted into and removed from the core of a boiling water reactor or the like to control the operation of the reactor. In conventional nuclear reactor control rods, as shown in FIGS. 4(A) and 4(B), a sheath 2 with a deep U-shaped cross section is attached to each protruding leg of a tie rod 1 with a cross-shaped cross section. A plurality of neutron absorption rods 4 are arranged in a row within each wing 3. The neutron absorbing rod 4 has a stainless steel cladding tube 5 filled with a neutron absorbing material 6 made of Bonn Carpide (84C). Reference numeral 7 is a tip structure member to which a handle 8 is attached, and this tip structure member 7 has a guide roller 9a that guides the insertion of the i and lJ control rods.
is installed (). Reference numeral 9b indicates a coolant water passage hole.

しかして、従来の原子炉用制御棒は、中性子吸収棒4内
に充填されたボロンカーバイドのボロン−10(10B
)が中性子と反応してHeガスやリチウムを発生さぼる
一方、中性子を吸収して10sが減耗し、反応度が低下
せしめられる。このように、原子炉用制御棒はボロンカ
ーバイドの10sが減耗して核的寿命が損われ、発生し
たト(eガスによる内圧上昇により機械的寿命が損われ
るため、ボロンカーバイドを使用した制御棒は寿命が比
較的短い等の問題があった。
Therefore, in the conventional nuclear reactor control rod, the neutron absorption rod 4 is filled with boron-10 (10B
) reacts with neutrons to generate He gas and lithium, while absorbing neutrons and depleting 10s, reducing the reactivity. In this way, control rods for nuclear reactors are depleted of 10 seconds of boron carbide, which impairs their nuclear lifespan, and the mechanical life is impaired due to an increase in internal pressure due to e-gas generated. had problems such as a relatively short lifespan.

この点から、原子炉用制御棒に装填される中性子吸収棒
にハフニウム(Hf)金属棒を採用することが考慮され
ている。ハフニウムはボロンカーバイドの中性子吸収棒
4を用いた制御棒の318〜6倍の長寿命化が図れるこ
とが知られている。
From this point of view, consideration has been given to using hafnium (Hf) metal rods as neutron absorption rods loaded into nuclear reactor control rods. It is known that hafnium can extend the lifespan by 318 to 6 times that of control rods using boron carbide neutron absorption rods 4.

しかしながら、ハフニウムは高価で重量が大きいため、
ハフニウム製中性子吸収棒をウィング内に配列させると
、原子炉用制御棒の全体重量が大幅に増加し、制御棒急
速作動時の制御棒駆動機構へのインバク1〜が非常に大
きくなる。このため、既存の原子炉ヘハフニウム製中性
子吸収棒を用いた制御棒をバックフィツトさせることが
困難であった。
However, hafnium is expensive and heavy, so
When hafnium neutron absorption rods are arranged in a wing, the overall weight of the control rod for a nuclear reactor increases significantly, and the impact on the control rod drive mechanism during rapid operation of the control rod becomes extremely large. For this reason, it has been difficult to backfit control rods that use neutron absorption rods made of hehafnium to existing nuclear reactors.

〔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、制御
棒の構造を簡素化して部品点数を減少させ、軽量構造で
も寿命の長い、長寿命型原子炉用制御棒を提供すること
を主な目的とする。
The present invention was made in consideration of the above-mentioned circumstances, and its main purpose is to simplify the structure of the control rod, reduce the number of parts, and provide a long-life control rod for a nuclear reactor that has a long life despite its lightweight structure. purpose.

本発明の他の目的は既存の原子炉にスムーズにバックフ
ィツトさせることができる原子炉用制御棒を提供するこ
とにある。
Another object of the present invention is to provide a nuclear reactor control rod that can be smoothly backfitted into an existing nuclear reactor.

〔発明の概要〕[Summary of the invention]

上述した目的を達成するために、本発明は十字状横断面
を有するタイロッド先端構造材および下端構造材を結合
させた原子炉用制御棒において、前記タイロッドの各突
脚に、深いU字状断面を有する金属板の開口部を取付け
てウィングを形成するとともに、上記金属板はハフニウ
ムを主成分とした金属製中性子吸収材で構成されたこと
を特徴とするものである。
In order to achieve the above-mentioned object, the present invention provides a control rod for a nuclear reactor in which a tie rod tip structure member and a lower end structure member having a cross-shaped cross section are combined, and each projecting leg of the tie rod has a deep U-shaped cross section. The wing is formed by attaching an opening in a metal plate having a metal plate having an opening, and the metal plate is made of a metal neutron absorbing material containing hafnium as a main component.

(発明の実施例) 以下、本発明に係る原子炉用制御棒の好ましい実施例に
ついて添付図面を参照して説明する。
(Embodiments of the Invention) Hereinafter, preferred embodiments of the control rod for a nuclear reactor according to the present invention will be described with reference to the accompanying drawings.

第1図は本発明に係る原子炉用制御棒を示すものであり
、図中符号10は制御棒のタイロッドを示す。タイロッ
ド10は横断面十字状をなすとともに、その先端には先
端構造材11が、下端には下端構造材(図示けず)が結
合されて一体化される。下端構造材は制御棒駆1Fl1
機構に結びついけられている。先端構造材11は制御棒
の挿入・抜出を案内するガイドローラ12が設けられる
。符号13は先端構造材11に取付けられた操作用のハ
ンドルを示ず。
FIG. 1 shows a control rod for a nuclear reactor according to the present invention, and reference numeral 10 in the figure indicates a tie rod of the control rod. The tie rod 10 has a cross-shaped cross section, and is integrated with a tip structure member 11 at its tip and a lower end structure member (not shown) at its lower end. The lower end structural material is control rod drive 1Fl1
It is tied to a mechanism. The tip structure member 11 is provided with guide rollers 12 that guide insertion and extraction of the control rod. Reference numeral 13 does not indicate an operating handle attached to the tip structure member 11.

一方、タイロッド10の各突脚に深いU字状断面を有づ
る金属板15が取付けられる。金属板15はタイロッド
10の各突脚に設けられた止めどン16に溶接等により
固着され、制御棒のウィング17が構成される。ウィン
グ17の金属板15はハフニウム(1−(f ’)やl
−1f −Z n合金等のハフニウムを主成分とする長
寿命型金属製中性子吸収材で構成される。ハフニウムは
中性子吸収能力が優れた金属材で、ボロンカーバイド(
B4C)の3〜6倍の寿命を有する。
On the other hand, a metal plate 15 having a deep U-shaped cross section is attached to each protruding leg of the tie rod 10. The metal plate 15 is fixed by welding or the like to a stopper 16 provided on each projecting leg of the tie rod 10, thereby forming a wing 17 of the control rod. The metal plate 15 of the wing 17 is made of hafnium (1-(f') or l
It is composed of a long-life metallic neutron absorbing material whose main component is hafnium, such as -1f-Zn alloy. Hafnium is a metal material with excellent neutron absorption ability, and is similar to boron carbide (
B4C) has a lifespan 3 to 6 times longer than that of B4C).

また、ウィング17は板厚1.5〜2.5#I#I程度
の薄い金属プレートで構成されるため、軽4構造であり
、このウィング17を補強させるために第2図に示づよ
うにタイロッド10の取付部近傍に補強材としてのステ
イフナ18が介装される。
In addition, since the wing 17 is composed of a thin metal plate with a thickness of about 1.5 to 2.5#I#I, it has a light 4 structure. A stiffener 18 as a reinforcing member is interposed near the attachment portion of the tie rod 10.

ステイフナ18はウィング17の内部空間19内をタイ
ロッド10の軸方向に平行に延びている。
The stiffener 18 extends in the interior space 19 of the wing 17 in parallel to the axial direction of the tie rod 10.

ステイフナ18はウィング17に溶接可能な金属材、好
ましくはハフニウムを主成分とした金属材で構成され、
ウィング17に溶着される。
The stiffener 18 is made of a metal material that can be welded to the wing 17, preferably a metal material mainly containing hafnium,
It is welded to the wing 17.

さらに、ウィング17はタイロッド10への取付部近傍
を除いて、膨出され、ステイフナ18の外側においてウ
ィング17の幅Wが拡幅される。
Further, the wing 17 is bulged out except in the vicinity of the attachment portion to the tie rod 10, and the width W of the wing 17 is widened outside the stiffener 18.

これにより、ウィング17の金属板15は、燃料集合体
のチI7ンネルボツクス20に近接して位置せしめられ
、かつウィング17の内部空間19に【よ減速材として
の冷却材(水)が存在するので反応度を大きくすること
ができる。すなわち、タイロッド10への取付部近傍を
除いてウィング17を拡幅さぼることにより、ウィング
17の金属板15は燃料集合体の表面に接近し、その分
だけ反応度を大きくさせることができる。その際、制御
棒の反応度を更に上昇さけるため、ウィング17の側端
付近の内部空間にハフニウムを主成分とした中性子吸収
棒を収容させてもよい。
As a result, the metal plate 15 of the wing 17 is positioned close to the channel box 20 of the fuel assembly, and the coolant (water) as a moderator is present in the internal space 19 of the wing 17. The degree of reactivity can be increased. That is, by widening and retracting the wing 17 except for the vicinity of the attachment portion to the tie rod 10, the metal plate 15 of the wing 17 approaches the surface of the fuel assembly, and the reactivity can be increased accordingly. At this time, in order to further avoid increasing the reactivity of the control rod, a neutron absorption rod containing hafnium as a main component may be accommodated in the internal space near the side end of the wing 17.

ところで、ウィング17の拡幅部にはタイロッド10の
軸方向に適宜離間して外側パッド22が設【づられ、こ
の外側パッド22によりヂャンネルボックス20に摺動
するようにして制御棒の挿入・引抜ぎが案内される。外
側パッド22に対応する位置には内側パッド23が装着
される。内側パッド23は、ウィング17の内部空間1
9の両側(片側でもよい。)に設けられて、間隔保持ス
ベーυとして機能し、シース状のウィング17の内部空
間19が過度に狭くなるのを防止している。
Incidentally, outer pads 22 are provided on the widened portion of the wing 17 at appropriate distances in the axial direction of the tie rod 10, and the outer pads 22 allow the control rods to be inserted and withdrawn by sliding against the channel box 20. Gi is guided. An inner pad 23 is attached to a position corresponding to the outer pad 22. The inner pad 23 covers the inner space 1 of the wing 17.
They are provided on both sides (or on one side) of the wing 9 and function as a spacer υ to prevent the internal space 19 of the sheath-like wing 17 from becoming excessively narrow.

内側パッド23と外側バッド22とは一体構造物として
もよい。
The inner pad 23 and the outer pad 22 may be an integral structure.

また、前記ウィング17の内側部、すなわちタイロッド
10側のウィング幅W、は、従来のウィングと同程度に
狭く形成される。これは、タイロッド近傍のバンドル内
出力が特に低くなるので、・ウィング17の幅を狭くし
、ウィング17の金属板15表面とチャンネルボックス
表面20との距離が大きくなるように設定し、タイロッ
ド近傍の出力の低下を抑制したものである。ウィング1
7の幅W1を狭くすることにより、タイロッド近傍の出
ガが増大するので、制御棒引抜時の異常出力上昇を有効
的に防止できる。また、制御棒挿入時におけるバンドル
内出力分布がより平坦化され、均一化される。
Further, the inner side of the wing 17, that is, the wing width W on the tie rod 10 side, is formed to be as narrow as a conventional wing. This is because the output in the bundle near the tie rods is particularly low. - The width of the wing 17 is narrowed, and the distance between the surface of the metal plate 15 of the wing 17 and the channel box surface 20 is set to be large. This suppresses the decrease in output. wing 1
By narrowing the width W1 of the control rod 7, the output near the tie rod increases, so an abnormal increase in output when the control rod is pulled out can be effectively prevented. Furthermore, the power distribution within the bundle when the control rods are inserted is further flattened and made uniform.

漬方、原子炉用制御棒のウィング17には罫線25がタ
イロッド10の軸方向に適宜離間して刻設される。W 
?’、il 25 +jタイロッド10の軸方向にほぼ
直交する方向に延びる一方、罫線25の途中には小孔2
6が穿設される。ウィング17の罫線25は小孔26を
境にしてウィング17の外側では凹設され、その内側で
は好ましくは凸段される。
On the wing 17 of the nuclear reactor control rod, ruled lines 25 are carved at appropriate intervals in the axial direction of the tie rod 10. W
? ', il 25 +j Extends in a direction substantially perpendicular to the axial direction of the tie rod 10, and has a small hole 2 in the middle of the ruled line 25.
6 is drilled. The ruled line 25 of the wing 17 is preferably concave on the outside of the wing 17 with the small hole 26 as a boundary, and is preferably stepped on the inside.

ウィング17に罫線25を施すことにより、制御棒に弾
力性を持たせ、変形を容易にし、制御棒の挿入・引抜き
がスムーズに行なわれるようにしたものである。
By forming the ruled lines 25 on the wing 17, the control rod is given elasticity and deformation is facilitated, so that insertion and withdrawal of the control rod can be performed smoothly.

なお、ウィング17の金属板15には冷却材の通水孔が
適宜穿設される。
Note that the metal plate 15 of the wing 17 is appropriately provided with water passage holes for the coolant.

〔発明の効果〕〔Effect of the invention〕

以上に述べたように、本発明に係る原子か用制御棒にお
いては、タイロッドの各突脚に、深いU字状断面を有す
る金属板の開口部を取付けてウィングを形成するととも
に、上記金属板は長寿命型金属製中性子吸収材で構成さ
れたから、ウィング内に多数の中性子吸収棒を配列する
必要がなく、部品点数が大幅に減少されて構造を簡素化
することができる。このため、重信の大ぎな金属製中性
子吸収材を用いても制御棒を軽量構造とすることができ
る。したがって、本発明の制御棒はB4Cを用いた従来
の制御棒の重信と、金属板の板厚を調節することにより
同程度の重さとすることができるので、制御棒急速作動
時に制御棒駆動機構に作用するインパクトを小さく抑え
ることができ、既存の原子炉にスムーズにバックフィツ
トざVることができ、しかも、制御棒の寿命を長くする
ことができるという効果を有する。
As described above, in the atomic control rod according to the present invention, an opening in a metal plate having a deep U-shaped cross section is attached to each protruding leg of the tie rod to form a wing, and the metal plate Since it is made of long-life metal neutron absorbing material, there is no need to arrange a large number of neutron absorbing rods in the wing, which greatly reduces the number of parts and simplifies the structure. For this reason, the control rod can have a lightweight structure even if a large metal neutron absorbing material is used. Therefore, the control rod of the present invention can be made to have the same weight as the conventional control rod using B4C by adjusting the thickness of the metal plate. This has the effect that the impact acting on the control rod can be suppressed to a small level, that it can be smoothly backfitted into an existing nuclear reactor, and that the life of the control rod can be extended.

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

第1図は本発明に係る原子炉用制御棒の一実施例を示す
図、第2図は第1図の■−■線に沿う平断面図、第3図
は第1図の■−■線に沿う縦断面図、第4図(A)は従
来の原子炉用制御棒を示す図、第4図(B)は第4図(
A)のB−8線に沿う平断面図である。 10・・・タイロッド、1・・・先端構造材、15・・
・金属板、17・・・ウィング、18・・・ステイフナ
、19.19a・・・ウィング幅、20・・・チャンネ
ルボックス表面、22・・・外側パッド、23・・・内
側パッド、25・・・罫線、26・・・小孔。 出願人代理人   波 多 野   久第3図 第4図
Fig. 1 is a diagram showing an embodiment of a control rod for a nuclear reactor according to the present invention, Fig. 2 is a plan cross-sectional view taken along the line ■-■ in Fig. 1, and Fig. 3 is a diagram showing an embodiment of the control rod for a nuclear reactor according to the present invention. 4(A) is a diagram showing a conventional nuclear reactor control rod, and FIG. 4(B) is a longitudinal sectional view taken along the line.
It is a plane cross-sectional view along the B-8 line of A). 10... Tie rod, 1... Tip structure material, 15...
・Metal plate, 17...Wing, 18...Stiffener, 19.19a...Wing width, 20...Channel box surface, 22...Outer pad, 23...Inner pad, 25... - Ruled line, 26...small hole. Applicant's agent Hisashi Hatano Figure 3 Figure 4

Claims (1)

【特許請求の範囲】 1、十字状横断面を有するタイロッドの先端および下端
に先端構造材および下端構造材を結合させた原子炉用制
御棒において、前記タイロッドの各突脚に、深いU字状
断面を有する金属板の開口側を取付けてウィングを形成
するとともに、上記金属板はハフニウムを主成分とした
金属製中性子吸収材で構成されたことを特徴とする原子
炉用制御棒。 2、金属板は、ハフニウムを主成分とした薄いプレート
状金属製中性子吸収材である特許請求の範囲第1項に記
載の原子炉用制御棒。 3、金属板はタイロッド取付部近傍を除いて膨出され、
ウィングの幅が拡幅された特許請求の範囲第1項に記載
の原子炉用制御棒。 4、金属板はタイロッドの軸方向にほぼ直交する罫線が
タイロッドの軸方向に適宜間隔をおいて設けられた特許
請求の範囲第1項に記載の原子炉用制御棒。
[Claims] 1. In a control rod for a nuclear reactor in which a tip structure member and a bottom structure member are connected to the tip and bottom ends of a tie rod having a cross-shaped cross section, each protruding leg of the tie rod has a deep U-shape. A control rod for a nuclear reactor, characterized in that a wing is formed by attaching an open side of a metal plate having a cross section, and the metal plate is made of a metal neutron absorbing material containing hafnium as a main component. 2. The control rod for a nuclear reactor according to claim 1, wherein the metal plate is a thin plate-shaped metal neutron absorbing material containing hafnium as a main component. 3. The metal plate is bulged out except near the tie rod attachment area,
A control rod for a nuclear reactor according to claim 1, wherein the width of the wing is increased. 4. The control rod for a nuclear reactor according to claim 1, wherein the metal plate is provided with ruled lines substantially perpendicular to the axial direction of the tie rod at appropriate intervals in the axial direction of the tie rod.
JP60019858A 1985-02-06 1985-02-06 Control rod for nuclear reactor Pending JPS61180187A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60019858A JPS61180187A (en) 1985-02-06 1985-02-06 Control rod for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60019858A JPS61180187A (en) 1985-02-06 1985-02-06 Control rod for nuclear reactor

Publications (1)

Publication Number Publication Date
JPS61180187A true JPS61180187A (en) 1986-08-12

Family

ID=12010925

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60019858A Pending JPS61180187A (en) 1985-02-06 1985-02-06 Control rod for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS61180187A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009042006A (en) * 2007-08-07 2009-02-26 Hitachi-Ge Nuclear Energy Ltd Control rod for boiling water reactor
JP2010230607A (en) * 2009-03-30 2010-10-14 Hitachi-Ge Nuclear Energy Ltd Control rod
JP2013054037A (en) * 2012-11-20 2013-03-21 Toshiba Corp Reactor control rod
JP2014178255A (en) * 2013-03-15 2014-09-25 Toshiba Corp Reactor control rod using high strength anticorrosive hafnium alloy, and high strength anticorrosive hafnium alloy for reactor control rod

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009042006A (en) * 2007-08-07 2009-02-26 Hitachi-Ge Nuclear Energy Ltd Control rod for boiling water reactor
JP2010230607A (en) * 2009-03-30 2010-10-14 Hitachi-Ge Nuclear Energy Ltd Control rod
JP2013054037A (en) * 2012-11-20 2013-03-21 Toshiba Corp Reactor control rod
JP2014178255A (en) * 2013-03-15 2014-09-25 Toshiba Corp Reactor control rod using high strength anticorrosive hafnium alloy, and high strength anticorrosive hafnium alloy for reactor control rod

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