JPH0961576A - Control rod for boiling water reactor and its manufacture - Google Patents

Control rod for boiling water reactor and its manufacture

Info

Publication number
JPH0961576A
JPH0961576A JP7220234A JP22023495A JPH0961576A JP H0961576 A JPH0961576 A JP H0961576A JP 7220234 A JP7220234 A JP 7220234A JP 22023495 A JP22023495 A JP 22023495A JP H0961576 A JPH0961576 A JP H0961576A
Authority
JP
Japan
Prior art keywords
tie rod
rod
sheath
boiling water
cross
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
JP7220234A
Other languages
Japanese (ja)
Inventor
Yasuyuki Goto
靖之 後藤
Norio Kawashima
範夫 川島
Hideaki Ishizaki
英昭 石崎
Takehiro Seto
武裕 瀬戸
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.)
Hitachi Engineering Co Ltd
Hitachi Ltd
Original Assignee
Hitachi Engineering Co Ltd
Hitachi 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 Hitachi Engineering Co Ltd, Hitachi Ltd filed Critical Hitachi Engineering Co Ltd
Priority to JP7220234A priority Critical patent/JPH0961576A/en
Publication of JPH0961576A publication Critical patent/JPH0961576A/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

Abstract

PROBLEM TO BE SOLVED: To provide a control rod having a structure superior in productivity. SOLUTION: This is a control rod 1 for a boiling water reactor formed by intermittently and partially welding a tie rod 4 having a cross-shaped section and a sheath 6 having a U-shape cross section and including reactivity control material 3 therein, and the tie rod 4 has a plurality of bevels 12, the sheath 6 has projection-like parts 2 of the same number as the bevels 12 at a position corresponding to the bevels 12, the bevels 12 and the projection-like parts 2 are abutted to each other and welded intermittently and partially.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【発明の属する技術分野】本発明は、沸騰水型原子炉に
用いられる制御棒に係り、特に生産性の点で好適な構造
を有する沸騰水型原子炉用制御棒及びその製造方法に関
する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a control rod for use in a boiling water reactor, and more particularly to a control rod for a boiling water reactor having a structure suitable for productivity and a method for manufacturing the same.

【0002】[0002]

【従来の技術】従来の沸騰水型原子炉用制御棒について
は、図3と図4に示すようなものがある。これによれ
ば、十字形の横断面形状を有するタイロッドの各辺の先
端部に、長手方向に長い開先が設けられた構造となって
いる。
2. Description of the Related Art Conventional boiling water reactor control rods include those shown in FIGS. According to this, the tie rod having a cross-shaped cross section has a structure in which a groove long in the longitudinal direction is provided at the tip of each side.

【0003】[0003]

【発明が解決しようとする課題】上記従来技術の制御棒
においては、開先がタイロッドの各辺の先端部の長手方
向の全長に亘って設けられているので、加工性に関し改
善する課題がある。従って、本発明の目的は、加工性が
良く生産性に優れた構造を有する制御棒及びその製造方
法を提供することにある。
In the above-mentioned conventional control rod, since the groove is provided over the entire length in the longitudinal direction of the tip end portion of each side of the tie rod, there is a problem of improving workability. . Therefore, it is an object of the present invention to provide a control rod having a structure with good workability and excellent productivity, and a manufacturing method thereof.

【0004】[0004]

【課題を解決するための手段】上記目的を達成する沸騰
水型原子炉用制御棒は、十字形の横断面形状を有するタ
イロッドと、U字形の横断面形状を有し内部に反応度制
御材を包含するシースとを間歇部分溶接してなる沸騰水
型原子炉用制御棒において、前記タイロッドは、前記シ
ースと溶接される間歇部分に対応した部位にのみ、開先
を有するものである。
A control rod for a boiling water nuclear reactor that achieves the above object comprises a tie rod having a cross-shaped cross-sectional shape and a reactivity control material having a U-shaped cross-sectional shape inside. In a boiling water nuclear reactor control rod obtained by intermittently welding a sheath including the above, the tie rod has a groove only at a portion corresponding to the intermittent portion to be welded to the sheath.

【0005】さらに、前記タイロッドは、複数の開先を
有し、前記シースは、前記開先に対応する位置に前記開
先と同数の凸状部位を有し、該凸状部位と前記開先とが
突合わされ、間歇部分溶接されているものでも良い。
Further, the tie rod has a plurality of grooves, and the sheath has the same number of convex portions as the grooves at a position corresponding to the grooves, the convex portions and the grooves. It is also possible that they are butted and are intermittently welded.

【0006】また、上記目的を達成する沸騰水型原子炉
用制御棒の製造方法は、十字形の横断面形状を有するタ
イロッドと、U字形の横断面形状を有し内部に反応度制
御材を包含するシースとを間歇部分溶接する沸騰水型原
子炉用制御棒の製造方法において、前記タイロッドに複
数の開先を設け、前記シースに前記開先に対応する位置
に前記開先と同数の凸状部位を設け、該凸状部位と前記
開先とを突合わし間歇部分溶接するものである。
Further, in a method of manufacturing a control rod for a boiling water reactor for achieving the above object, a tie rod having a cross-shaped cross section and a reactivity control material having a U-shaped cross-section are provided inside. In a method for manufacturing a boiling water reactor control rod for intermittently welding a sheath to be included, a plurality of grooves are provided in the tie rod, and the sheath has the same number of protrusions as the grooves at a position corresponding to the groove. A grooved portion is provided, and the convex portion and the groove are butted against each other and intermittent welding is performed.

【0007】[0007]

【発明の実施の形態】以下、本発明の実施の形態につい
て、図面を参照し説明する。図1は、本発明による一実
施例の沸騰水型原子炉用制御棒の構造を示す図である。
図1に示すように、本実施例による沸騰水型原子炉用の
制御棒1は、ハンドル5及び下部支持部材8とタイロッ
ド4とを溶接で結合した骨組み構造であり、U字形の横
断面形状を有するシース6に上部反応度制御材3Uと下
部反応度制御材3Lとを包含し、ハンドル5に上部反応
度制御材3Uを吊り下げるための舌状部5’を有し、 下
部支持部材8に下部反応度制御材3Lを結合するための
舌状部8’を有した構造である。
Embodiments of the present invention will be described below with reference to the drawings. FIG. 1 is a view showing the structure of a boiling water reactor control rod according to an embodiment of the present invention.
As shown in FIG. 1, a control rod 1 for a boiling water reactor according to this embodiment has a frame structure in which a handle 5, a lower support member 8 and a tie rod 4 are welded together, and has a U-shaped cross section. A sheath 6 having a lower reactivity control material 3U and a lower reactivity control material 3L, and a handle 5 having a tongue 5'for suspending the upper reactivity control material 3U. The structure has a tongue portion 8'for connecting the lower reactivity control material 3L.

【0008】そして、タイロッド4に設けた複数の凹状
の形状からなる開先12と、該開先12に対応する位置
に開先個数と同数だけシース6に設けた凸状部位2とを
突合わせて、間歇部分溶接した構造である。また、下部
支持部材8に制御棒駆動機構装置と連結するためのコネ
クタ10が溶接により結合された構造である。
Then, a plurality of concave grooves 12 provided on the tie rod 4 and the convex portions 2 provided on the sheath 6 at the positions corresponding to the grooves 12 by the same number as the number of the grooves are butted. It is a structure that is intermittently welded. Further, the lower support member 8 has a structure in which a connector 10 for connecting to the control rod drive mechanism device is joined by welding.

【0009】図2は、図1のA−A断面及びB−B断面
を示す図である。図2(a)は、図1に示す制御棒の翼断
面A−Aであり、図2(b)は、翼断面B−Bを示す図であ
る。
FIG. 2 is a view showing an AA cross section and a BB cross section of FIG. 2A is a blade cross section AA of the control rod shown in FIG. 1, and FIG. 2B is a blade cross section BB.

【0010】図2に示すように、翼断面A−Aは、シース
6とタイロッド4との溶接しない部位の断面であり、翼
断面B−Bは、シース6とタイロッド4とを溶接する部位
の断面である。図2(a)に示すように当該溶接しない部
位において、シース6とタイロッド4とは溶接されてお
らず、シース6とタイロッド4とに間隙20がある。ま
た、タイロッド4の各辺の先端部には開先12が設けら
れていない。一方、図2(b)に示すように当該溶接する
部位において、シース6の凸状部位2は、タイロッド4
の各辺の先端部に設けられた開先12に差し込まれ、突
合せ溶接により結合される。
As shown in FIG. 2, the blade cross section A-A is a cross section of a portion where the sheath 6 and the tie rod 4 are not welded, and the blade cross section BB is a portion where the sheath 6 and the tie rod 4 are welded. It is a cross section. As shown in FIG. 2A, the sheath 6 and the tie rod 4 are not welded at the non-welded portion, and a gap 20 exists between the sheath 6 and the tie rod 4. Further, the groove 12 is not provided at the tip of each side of the tie rod 4. On the other hand, as shown in FIG. 2 (b), in the welding portion, the convex portion 2 of the sheath 6 is
Is inserted into the groove 12 provided at the tip of each side, and is joined by butt welding.

【0011】図1及び図2から判るように、シース6の
タイロッド4と取付ける辺の凸状部位2は、長手方向に
断続的に複数箇所に有しており、タイロッド4の各辺の
先端部には、ハンドル5及びタイロッド4、ならびに、
下部支持部材8及びタイロッド4を溶接する場合に、タ
イロッド4の長手方向の寸法が変化することが回避され
る。また、シース6の凸状部位2の製作公差等を考慮し
ても溶接作業が容易となる。したがって、本発明による
制御棒の構成によれば、十字形の横断面形状を有するタ
イロッドの各辺の先端部の開先を、長手方向に複数箇所
設けたことで、開先加工工数が減ると共に、加工時のタ
イロッドの撓みに伴う製造公差の狂いが少なくなり、指
定された開先寸法に容易に加工することができ、制御棒
の生産性の向上に有効である。
As can be seen from FIG. 1 and FIG. 2, the convex portions 2 of the side of the sheath 6 to be attached to the tie rod 4 are intermittently provided at a plurality of locations in the longitudinal direction, and the tip end portion of each side of the tie rod 4 is provided. Includes a handle 5 and a tie rod 4, and
When welding the lower support member 8 and the tie rod 4, it is avoided that the longitudinal dimension of the tie rod 4 changes. Further, the welding work is facilitated even in consideration of the manufacturing tolerance of the convex portion 2 of the sheath 6. Therefore, according to the configuration of the control rod according to the present invention, by providing a plurality of groove portions at the tip of each side of the tie rod having a cross-shaped cross-sectional shape in the longitudinal direction, the groove processing man-hour is reduced and The deviation of the manufacturing tolerance due to the bending of the tie rod during processing is reduced, and the specified groove dimension can be easily processed, which is effective in improving the productivity of the control rod.

【0012】次に、具体的な寸法例について、上記のシ
ース6のタイロッド4に取付ける辺の凸状部位2と、該
凸状部位2に相対峙するようにタイロッド4の各辺の先
端部に間歇的に複数設けた開先12とに対して、以下に
説明する。シース6のタイロッド4に取付ける辺の長手
方向に断続的に複数箇所を有する凸状部位2は、シース
6の長手方向の両端部に約7mmの位置から約17mmの凸
状部位2が2箇所、また、両端の凸状部位2から約12
3mmの間隔で約27mmの凸状部位2が23箇所、併せて
計25箇所設けられる。そして、前述した溶接及び製作
公差の影響を考慮してこれらシース6の凸状部位2と相
対峙するように、タイロッド4の各辺の先端部に開先1
2は、タイロッド4の両端部に40mmの開先12が2箇
所、 また、 両端の開先12から100mm間隔に50mm
の開先12が23箇所、併せて計25箇所設けられる。
Next, regarding specific dimensions, the convex portion 2 of the side of the sheath 6 to be attached to the tie rod 4 and the tip portion of each side of the tie rod 4 so as to face the convex portion 2 relative to each other. A plurality of grooves 12 intermittently provided will be described below. The convex portion 2 having a plurality of intermittent portions in the longitudinal direction of the side of the sheath 6 to be attached to the tie rod 4 has two convex portions 2 of about 7 mm to about 17 mm at both ends in the longitudinal direction of the sheath 6, In addition, about 12 from the convex portion 2 at both ends
23 convex portions 2 of about 27 mm are provided at intervals of 3 mm, and a total of 25 convex portions 2 are provided. Then, in consideration of the above-mentioned welding and manufacturing tolerances, the groove 1 is formed at the tip of each side of the tie rod 4 so as to face the convex portion 2 of the sheath 6.
2 has two 40 mm grooves 12 at both ends of the tie rod 4, and 50 mm at 100 mm intervals from both ends of the groove 12.
The groove 12 of 23 is provided at a total of 25 locations.

【0013】ここで、従来の沸騰水型原子炉用制御棒に
ついて説明する。従来の沸騰水型原子炉用制御棒の構造
を図3に示し、図3のa−a断面及びb−b断面を図4
(A)及び(B)に示す。図3及び図4において、沸騰水型
原子炉用の制御棒1は、十字形の横断面形状のタイロッ
ド4の各辺に、U字形の横断面形状を有するシース6を
取付け、U字形の横断面形状を有するシース6の内部に
反応度制御材3を包含し、U字形の横断面形状を有する
シース6の上部と上部反応度制御材3Uを制御棒挿入端
側に配置するハンドル5で固定し、シース6の下部と下
部支持部材8で固定し、十字形の横断面形状のタイロッ
ド4とシース6のタイロッド4に取付ける辺の長手方向
複数箇所の凸状部位2と固定した構造となっている。
Now, a conventional boiling water reactor control rod will be described. The structure of a conventional boiling water reactor control rod is shown in FIG. 3, and the aa cross section and the bb cross section of FIG. 3 are shown in FIG.
Shown in (A) and (B). 3 and 4, a control rod 1 for a boiling water nuclear reactor has a tie rod 4 having a cross-shaped cross section, and a sheath 6 having a U-shaped cross-section is attached to each side of the tie rod 4 to cross the U-shaped cross section. The reactivity control material 3 is included in the sheath 6 having a surface shape, and the upper portion of the sheath 6 having a U-shaped cross section and the upper reactivity control material 3U are fixed by the handle 5 arranged on the control rod insertion end side. Then, the lower portion of the sheath 6 and the lower support member 8 are fixed, and the tie rod 4 having a cross-shaped cross section and the convex portions 2 at a plurality of longitudinal sides of the side of the sheath 6 attached to the tie rod 4 are fixed. There is.

【0014】この従来構造の制御棒1は、十字形の横断
面形状のタイロッド4の各辺の先端部に図4に示すよう
な形状の開先12を有し、該開先12は、十字形の横断
面形状のタイロッド4の長手方向の全長に亘って設けら
れた構造である。また、U字形の横断面形状を有するシ
ース6は、十字形の横断面形状のタイロッド4に取付け
る辺に凸状部位2を長手方向に断続的に複数箇所に有し
ている。このU字形の横断面形状を有するシース6のタ
イロッド4に取付ける辺の凸状部位2と、前述した十字
形の横断面形状のタイロッド4の各辺の先端部の開先1
2とを取付け、溶接する構造としている。
The control rod 1 of this conventional structure has a groove 12 having a shape as shown in FIG. 4 at the tip of each side of a tie rod 4 having a cross-shaped cross section. This is a structure provided over the entire length of the tie rod 4 having a V-shaped cross section in the longitudinal direction. Further, the sheath 6 having a U-shaped cross-sectional shape has convex portions 2 on a side to be attached to the tie rod 4 having a cross-shaped cross-sectional shape, intermittently in a plurality of positions in the longitudinal direction. The convex portion 2 of the side of the sheath 6 having the U-shaped cross section attached to the tie rod 4, and the groove 1 at the tip of each side of the above-mentioned cross-shaped tie rod 4 having the cross section.
2 is attached and welded.

【0015】一方、本発明による実施例のように複数箇
所の開先を設けたことにより、図3と図4に示す従来の
制御棒におけるタイロッド4の開先の長手方向(制御棒
の軸方向)の長さに対し、本発明による制御棒における
開先の長手方向の長さが、開先1箇所当たりで約1/75の
長さとなる。これによって、タイロッド4の開先を加工
する場合、タイロッド4の軸方向の撓みに伴う嵌合公差
の狂いが少なくなり、すなわち、タイロッド4の撓みを
考慮することなく指定された製作寸法に開先を加工する
ことができ、製造効率の向上が図られる。なお、上記嵌
合公差とはタイロッド4とシース6との嵌合寸法であ
る。 従って、従来に比べ開先加工工数が減る
と共に、加工時のタイロッドの撓みに伴う製造公差の狂
いが少なくなり、指定された開先寸法に容易に加工する
ことができ、制御棒の生産性の向上に有効である。
On the other hand, by providing a plurality of grooves as in the embodiment of the present invention, the longitudinal direction of the groove of the tie rod 4 in the conventional control rod shown in FIGS. 3 and 4 (the axial direction of the control rod). ), The length of the groove in the control rod according to the present invention in the longitudinal direction is about 1/75 per groove. As a result, when the groove of the tie rod 4 is machined, the deviation of the fitting tolerance due to the bending of the tie rod 4 in the axial direction is reduced, that is, the groove is manufactured to a specified manufacturing dimension without considering the bending of the tie rod 4. Can be processed, and manufacturing efficiency can be improved. The fitting tolerance is a fitting dimension of the tie rod 4 and the sheath 6. Therefore, the number of man-hours required for machining the groove is reduced as compared with the conventional method, and the deviation of the manufacturing tolerance caused by the bending of the tie rod during machining is reduced. It is effective for improvement.

【0016】図5は、沸騰水型原子炉用制御棒の製造工
程の従来と本発明の比較を示す図である。図5(A)は、
従来の製造工程を示す図である。図5(B)は、本発明に
よる沸騰水型原子炉用制御棒の製造工程の一実施例を示
す図である。図5を参照し、制御棒の製造工程について
説明する。図5(A)に示す従来の製造工程は、(a)制
御棒を構成する各部材の材料として適切な仕様、寸法で
あるか確認する。次に(b)十字型の横断面を有するタ
イロッド4の各辺の先端部に長手方向へ全長に開先の加
工を実施する。 次に(c)タイロッド4の寸法検査を
実施し、タイロッド4が指定寸法範囲内であるならば次
の工程である(e)タイロッド4の上下端部溶接を実施
する。しかし指定寸法範囲外の場合は、(d)タイロッ
ド4の開先を手作業で再加工し、更に再度、タイロッド
4の寸法検査を実施して、次の工程である(e)タイロ
ッド4の上下端部溶接を実施する。
FIG. 5 is a view showing a comparison between the conventional manufacturing method and the present invention of the manufacturing process of the boiling water reactor control rod. Figure 5 (A) shows
It is a figure which shows the conventional manufacturing process. FIG. 5 (B) is a diagram showing an embodiment of a process of manufacturing a control rod for a boiling water reactor according to the present invention. The manufacturing process of the control rod will be described with reference to FIG. In the conventional manufacturing process shown in FIG. 5A, (a) it is confirmed whether the specifications and dimensions are appropriate as the material of each member constituting the control rod. Next, (b) a groove is formed over the entire length in the longitudinal direction at the tip of each side of the tie rod 4 having a cross-shaped cross section. Next, (c) dimensional inspection of the tie rod 4 is performed, and if the tie rod 4 is within the specified dimension range, the next step (e) welding of the upper and lower ends of the tie rod 4 is performed. However, if the size is out of the specified size range, (d) the groove of the tie rod 4 is manually reprocessed, and the dimensional inspection of the tie rod 4 is performed again, and the next step is (e) the vertical movement of the tie rod 4. Perform edge welding.

【0017】これは、制御棒挿入端側に配置するハンド
ル5及び制御棒駆動装置連結側に配置する下部支持部材
8で十字形の横断面形状のタイロッド4と溶接すること
である。次に(f)この溶接した箇所に非破壊検査を実
施し、次に(g)反応度制御材を制御棒挿入端側に配置
するハンドル4及び制御棒駆動装置連結側に配置する下
部支持部材8に組み込み、(h)反応度制御材寸法検査
を実施し、(i)U字形の横断面形状を有するシース6
においてタイロッド4に取付ける辺の凸状部位2とタイ
ロッド4の各辺の先端部に設けられた開先とを溶接し、
(j)外観検査,寸法検査及び非破壊検査を実施し、
(k)洗浄、(l)梱包する工程である。
This is to weld the tie rod 4 having a cross-shaped cross section with the handle 5 arranged on the control rod insertion end side and the lower support member 8 arranged on the control rod drive device connecting side. Next, (f) non-destructive inspection is performed on the welded portion, and then (g) the handle 4 for disposing the reactivity control material on the control rod insertion end side and the lower support member for disposing on the control rod drive device coupling side. 8), (h) Reactivity control material dimensional inspection was performed, and (i) Sheath 6 having U-shaped cross section
In, welding the convex portion 2 of the side to be attached to the tie rod 4 and the groove provided at the tip of each side of the tie rod 4,
(J) Perform visual inspection, dimensional inspection and non-destructive inspection,
(K) Washing, (l) Packing process.

【0018】図5(A)に示す従来の製造工程は、前述し
た(b)工程において、タイロッド4の加工は、タイロ
ッド4の各辺の先端部に全長に開先を施す場合である。
このタイロッド4の各辺の先端部の開先加工手順はいく
つか考えられるが、例えば、タイロッド4を固定し、指
定された開先の寸法に加工するための治具を、タイロッ
ド4の開先を加工する前に位置決めしただけで、タイロ
ッド4の全長の開先加工を行うことが考えられる。しか
し該加工手順は、タイロッド4の全長が(一般に、4メ
ートル弱と)長いため、タイロッド4の軸方向のたわ
み、製造公差の影響で指定された開先寸法から外れる場
合がある。
In the conventional manufacturing process shown in FIG. 5 (A), the tie rod 4 is processed in the above-mentioned step (b) when the groove is provided at the tip of each side of the tie rod 4 over the entire length.
Although there are several possible groove processing procedures for the tip of each side of the tie rod 4, for example, a jig for fixing the tie rod 4 and processing it to a specified groove size is used. It is conceivable that the groove is machined over the entire length of the tie rod 4 simply by positioning it before machining. However, in the processing procedure, since the total length of the tie rod 4 is long (generally less than 4 meters), the tie rod 4 may deviate from the designated groove dimension due to the axial deflection and manufacturing tolerances.

【0019】また、タイロッド4の各辺の先端部の開先
を指定された寸法にするために、タイロッド4の軸方向
のたわみ、製造公差の影響等を予め考慮しながら加工す
る手順としても、寸法精度が得られ難く、指定された寸
法にするため再加工する必要がある。さらに、この全長
開先加工工程は、制御棒製作工程において大きな部分を
占めており、生産性の点で課題のある工程でもある。
Also, in order to make the groove of the tip of each side of the tie rod 4 a specified dimension, the procedure of processing while considering in advance the axial deflection of the tie rod 4, the influence of manufacturing tolerances, etc. It is difficult to obtain the dimensional accuracy, and it is necessary to rework to obtain the specified dimensions. Further, this full length groove processing step occupies a large part in the control rod manufacturing step, and is also a step with a problem in terms of productivity.

【0020】これに対し、図5(B)に示す本発明による
(b)'工程は、タイロッド4の加工において、タイロッ
ド4の各辺の先端部にシース6と溶接される間歇部分に
対応した部位にのみ、開先を有する開先加工を施す場合
である。これによって、開先加工によるタイロッド4の
軸方向のたわみ、製造公差の影響等がなくなるので、
(d)タイロッド再加工と、タイロッドを再加工した後
の(c)タイロッド寸法の再検査を必要としないものと
なる。したがって、製造効率が向上し生産性に優れた制
御棒が提供される効果が得られる。
On the other hand, the step (b) 'according to the present invention shown in FIG. 5 (B) corresponds to an intermittent portion which is welded to the sheath 6 at the tip of each side of the tie rod 4 in the processing of the tie rod 4. This is a case where the groove processing having the groove is applied only to the portion. This eliminates the axial deflection of the tie rod 4 due to the groove processing, the influence of manufacturing tolerances, etc.
This eliminates the need for (d) tie rod rework and (c) tie rod dimension re-inspection after tie rod rework. Therefore, the effect of providing a control rod with improved manufacturing efficiency and excellent productivity can be obtained.

【0021】[0021]

【発明の効果】溶接作業に対するタイロッドの撓みや製
作公差を配慮することなくタイロッドの開先加工が実施
できるようになり、製造効率が向上し生産性に優れた沸
騰水型原子炉用制御棒が提供される効果がある。
[Advantages of the Invention] A control rod for a boiling water nuclear reactor, which can be grooved for tie rods without considering bending of the tie rods during welding work and manufacturing tolerances, has improved manufacturing efficiency and is excellent in productivity. There is an effect provided.

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

【図1】本発明による一実施例の沸騰水型原子炉用制御
棒の構造を示す図である。
FIG. 1 is a view showing the structure of a boiling water reactor control rod according to an embodiment of the present invention.

【図2】図1のA−A断面及びB−B断面を示す図であ
る。
FIG. 2 is a diagram showing an AA cross section and a BB cross section of FIG. 1;

【図3】従来の沸騰水型原子炉用制御棒の構造を示す図
である
FIG. 3 is a view showing the structure of a conventional boiling water reactor control rod.

【図4】図3のa−a断面及びb−b断面を示す図であ
る。
FIG. 4 is a diagram showing an aa cross section and a bb cross section of FIG. 3;

【図5】沸騰水型原子炉用制御棒の製造工程の従来と本
発明の比較を示す図である。
FIG. 5 is a diagram showing a comparison between the conventional manufacturing process of the control rod for a boiling water reactor and the present invention.

【符号の説明】[Explanation of symbols]

1…制御棒、2…凸状部位、3…反応度制御材、3U…
上部反応度制御材、3L…下部反応度制御材、4…タイ
ロッド、5…ハンドル、5’,8’…舌状部、6…シー
ス、8…下部支持部材、10…コネクタ、12…開先、
20…間隙
1 ... Control rod, 2 ... Convex part, 3 ... Reactivity control material, 3U ...
Upper reactivity control material, 3L ... Lower reactivity control material, 4 ... Tie rod, 5 ... Handle, 5 ', 8' ... Tongue, 6 ... Sheath, 8 ... Lower support member, 10 ... Connector, 12 ... Groove ,
20 ... Gap

フロントページの続き (72)発明者 石崎 英昭 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 瀬戸 武裕 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所日立工場内Front page continuation (72) Inventor Hideaki Ishizaki 3-1-1 Sachimachi, Hitachi City, Ibaraki Hitachi Ltd. Hitachi factory (72) Inventor Takehiro Seto 3-1-1, Sachimachi, Hitachi, Ibaraki Stock company Hitachi Ltd.Hitachi factory

Claims (3)

【特許請求の範囲】[Claims] 【請求項1】十字形の横断面形状を有するタイロッド
と、U字形の横断面形状を有し内部に反応度制御材を包
含するシースとを間歇部分溶接してなる沸騰水型原子炉
用制御棒において、 前記タイロッドは、前記シースと溶接される間歇部分に
対応した部位にのみ、開先を有することを特徴とする沸
騰水型原子炉用制御棒。
1. A control for a boiling water reactor, comprising intermittently welding a tie rod having a cross-shaped cross-section and a sheath having a U-shaped cross-section and containing a reactivity control material inside. In the rod, the control rod for a boiling water reactor, wherein the tie rod has a groove only in a portion corresponding to an intermittent portion welded to the sheath.
【請求項2】十字形の横断面形状を有するタイロッド
と、U字形の横断面形状を有し内部に反応度制御材を包
含するシースとを間歇部分溶接してなる沸騰水型原子炉
用制御棒において、 前記タイロッドは、複数の開先を有し、前記シースは、
前記開先に対応する位置に前記開先と同数の凸状部位を
有し、該凸状部位と前記開先とが突合わされ、間歇部分
溶接されていることを特徴とする沸騰水型原子炉用制御
棒。
2. A control for a boiling water reactor, which is obtained by intermittently welding a tie rod having a cross-shaped cross-sectional shape and a sheath having a U-shaped cross-sectional shape and containing a reactivity control material inside. In the rod, the tie rod has a plurality of grooves, and the sheath is
A boiling water nuclear reactor characterized in that it has the same number of convex portions as the grooves at positions corresponding to the grooves, and the convex portions and the grooves are butted against each other and intermittently welded. Control rod.
【請求項3】十字形の横断面形状を有するタイロッド
と、U字形の横断面形状を有し内部に反応度制御材を包
含するシースとを間歇部分溶接する沸騰水型原子炉用制
御棒の製造方法において、 前記タイロッドに複数の開先を設け、前記シースに前記
開先に対応する位置に前記開先と同数の凸状部位を設
け、該凸状部位と前記開先とを突合わし間歇部分溶接す
ることを特徴とする沸騰水型原子炉用制御棒の製造方
法。
3. A control rod for a boiling water reactor in which a tie rod having a cross-shaped cross-section and a sheath having a U-shaped cross-section and containing a reactivity control material inside are intermittently welded. In the manufacturing method, the tie rod is provided with a plurality of grooves, the sheath is provided with the same number of convex portions as the grooves at a position corresponding to the grooves, and the convex portions and the grooves are abutted to each other to be intermittent. A method of manufacturing a boiling water reactor control rod, characterized by partial welding.
JP7220234A 1995-08-29 1995-08-29 Control rod for boiling water reactor and its manufacture Pending JPH0961576A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP7220234A JPH0961576A (en) 1995-08-29 1995-08-29 Control rod for boiling water reactor and its manufacture

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP7220234A JPH0961576A (en) 1995-08-29 1995-08-29 Control rod for boiling water reactor and its manufacture

Publications (1)

Publication Number Publication Date
JPH0961576A true JPH0961576A (en) 1997-03-07

Family

ID=16747997

Family Applications (1)

Application Number Title Priority Date Filing Date
JP7220234A Pending JPH0961576A (en) 1995-08-29 1995-08-29 Control rod for boiling water reactor and its manufacture

Country Status (1)

Country Link
JP (1) JPH0961576A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6654438B1 (en) 2000-08-30 2003-11-25 Hitachi, Ltd. Control rod for boiling water reactor, unit for control rod and production method of control rod
US6735266B1 (en) * 2001-12-17 2004-05-11 Hitachi, Ltd. Control rod for boiling water reactor and method for manufacturing the same
JP2009041994A (en) * 2007-08-07 2009-02-26 Hitachi-Ge Nuclear Energy Ltd Control rod for boiling water reactor
JP2009052967A (en) * 2007-08-24 2009-03-12 Hitachi-Ge Nuclear Energy Ltd Control rod and method for manufacturing the same
JP2012068123A (en) * 2010-09-24 2012-04-05 Hitachi-Ge Nuclear Energy Ltd Control rod lifetime evaluation method and control rod lifetime evaluation device

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6654438B1 (en) 2000-08-30 2003-11-25 Hitachi, Ltd. Control rod for boiling water reactor, unit for control rod and production method of control rod
US6735266B1 (en) * 2001-12-17 2004-05-11 Hitachi, Ltd. Control rod for boiling water reactor and method for manufacturing the same
US6882696B2 (en) * 2001-12-17 2005-04-19 Hitachi, Ltd. Control rod for boiling water reactor and method for manufacturing the same
JP2009041994A (en) * 2007-08-07 2009-02-26 Hitachi-Ge Nuclear Energy Ltd Control rod for boiling water reactor
JP2009052967A (en) * 2007-08-24 2009-03-12 Hitachi-Ge Nuclear Energy Ltd Control rod and method for manufacturing the same
JP2012068123A (en) * 2010-09-24 2012-04-05 Hitachi-Ge Nuclear Energy Ltd Control rod lifetime evaluation method and control rod lifetime evaluation device

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