JP2002168983A - Method of manufacturing control rod for pressurized water reactor - Google Patents

Method of manufacturing control rod for pressurized water reactor

Info

Publication number
JP2002168983A
JP2002168983A JP2000365706A JP2000365706A JP2002168983A JP 2002168983 A JP2002168983 A JP 2002168983A JP 2000365706 A JP2000365706 A JP 2000365706A JP 2000365706 A JP2000365706 A JP 2000365706A JP 2002168983 A JP2002168983 A JP 2002168983A
Authority
JP
Japan
Prior art keywords
cladding tube
end plug
control rod
coating
welding
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
JP2000365706A
Other languages
Japanese (ja)
Inventor
Takaaki Kitagawa
敬明 北川
Juntaro Shimizu
純太郎 清水
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries 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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP2000365706A priority Critical patent/JP2002168983A/en
Publication of JP2002168983A publication Critical patent/JP2002168983A/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 prevent occurrence and progress of contact wear of a control rod for a pressurized water reactor. SOLUTION: The control rod 40 is composed of a cover pipe 7, upper and lower end plugs 9 and 11 respectively joined to upper and lower ends of the cover pipe 7, and a neutron absorber 13 and a spring 15 put inside the cover pipe 7. The method of manufacturing the control rod 40 is composed of assembly through processes of joining the upper end plug 9 to the cover pipe 7 by a weld 41, applying a coating 43 on outer circumferential faces of the weld 41 and the cladding tube 7, inserting the neutron absorber 13 and the spring 15 inside the cladding tube 7, joining the cladding tube 7 and the lower end plug 11 by a weld 45, and applying a surface coating 47 on outer circumferential faces of the lower end plug 11 and the weld 45.

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、加圧水型原子炉用
制御棒に関し、特に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 a pressurized water reactor, and more particularly to a method for manufacturing the control rod.

【0002】[0002]

【従来の技術】加圧水型原子炉用制御棒は、一般に図5
に示すような制御棒クラスタの形で使用される。この構
造を概説すると、図5において、制御棒クラスタ1は、
制御棒駆動装置に連結されるスパイダ3とその放射状ベ
ーンに1本毎に上端が連結された複数の制御棒5とから
構成される。この制御棒5の構造を図6及び図7を参照
して説明すると、中空の被覆管7の上端及び下端に上部
端栓9及び下部端栓11が溶接されていて、内部には中
性子吸収材13とばね15が入れられている。図7に特
に示すように、被覆管7の外面にはクロムメッキ17が
施されている。上部端栓9の上部にあるねじ部がスパイ
ダ3との連結に使用される。
2. Description of the Related Art A control rod for a pressurized water reactor is generally constructed as shown in FIG.
It is used in the form of a control rod cluster as shown in FIG. To outline this structure, in FIG. 5, the control rod cluster 1
It comprises a spider 3 connected to a control rod drive and a plurality of control rods 5 each having an upper end connected to its radial vane. The structure of the control rod 5 will be described with reference to FIGS. 6 and 7. An upper end plug 9 and a lower end plug 11 are welded to the upper end and the lower end of a hollow cladding tube 7, and a neutron absorbing material is provided inside. 13 and a spring 15 are contained. As particularly shown in FIG. 7, the outer surface of the cladding tube 7 is provided with a chrome plating 17. The screw portion at the upper part of the upper end plug 9 is used for connection with the spider 3.

【0003】上述のような構造の制御棒クラスタ1は、
炉心を構成する燃料集合体の制御棒案内シンブルに制御
棒5が挿脱されるように使用されるが、図8にそのよう
な燃料集合体の構造の一例が概念的に示されている。図
8を参照するに、燃料集合体20の構造を概説すると、
上部ノズル21と下部ノズル23は、複数の互いに平行
な制御棒案内シンブル25によって連結されている。案
内シンブル25には、複数の支持格子27が間隔を置い
て固定されており、その複数の格子開口に複数の燃料棒
29が1本ずつ挿入され、支持されている。原子炉の炉
心は、このような燃料集合体20が多数隣接するように
装荷されて形成される。
The control rod cluster 1 having the above-described structure is
The control rod 5 is used to be inserted into and removed from the control rod guide thimble of the fuel assembly constituting the core. FIG. 8 conceptually shows an example of the structure of such a fuel assembly. Referring to FIG. 8, the structure of the fuel assembly 20 will be outlined.
The upper nozzle 21 and the lower nozzle 23 are connected by a plurality of parallel control rod guide thimbles 25. A plurality of support grids 27 are fixed to the guide thimble 25 at intervals, and a plurality of fuel rods 29 are inserted and supported one by one in the plurality of grid openings. The core of a nuclear reactor is formed by loading a large number of such fuel assemblies 20 adjacent to each other.

【0004】以上のような燃料集合体20から構成され
る炉心に、制御棒クラスタ1の制御棒5を挿脱するに
は、図示しない原子炉容器の上蓋に立設された制御棒駆
動装置が使用されるが、炉心と上蓋との間には、図9乃
至図11に示される制御棒クラスタ案内管構造体が使用
される。これを概説すると、炉心の直上部にある上部炉
心板31と更にその上方にある上部炉心支持板33に案
内管構造体35が支持されている。案内管構造体35の
外囲体は断面がほぼ正方形の筒状体37であり、その中
にカードと称する制御棒5の案内部材39a〜39jが
上下方向に間隔を置いて設けられている。原子炉の定格
出力運転時において、制御棒クラスタ1はほぼこの中に
引き上げられて支持されるから、カード39a〜39j
がその制御棒5に接触してこれを側方から支承する。案
内管構造体35の下部はコンティニュアスと称され、特
に図10に良く示されている。図10に示すように、こ
の部分では筒状体37に大きな開口があり、白抜き矢印
の如く流れてきた冷却材の一部がその開口を通って外向
きに流れる。定格出力運転時において、制御棒クラスタ
1の制御棒5の下端部は、図示するように燃料集合体2
0の上端部内にある。
In order to insert and remove the control rods 5 of the control rod cluster 1 into and from the core constituted by the fuel assemblies 20 as described above, a control rod driving device erected on the upper lid of a reactor vessel (not shown) is used. The control rod cluster guide tube structure shown in FIGS. 9 to 11 is used between the core and the top lid. In brief, the guide tube structure 35 is supported by an upper core plate 31 immediately above the core and an upper core support plate 33 further above. The outer circumference of the guide tube structure 35 is a cylindrical body 37 having a substantially square cross section, in which guide members 39a to 39j of control rods 5 called cards are provided at intervals in the vertical direction. During the rated output operation of the reactor, the control rod cluster 1 is almost lifted up and supported therein, so that the cards 39a to 39j
Contacts the control rod 5 and supports it from the side. The lower part of the guide tube structure 35 is called continuous and is particularly well shown in FIG. As shown in FIG. 10, a large opening is formed in the cylindrical body 37 in this portion, and a part of the coolant flowing as indicated by the white arrow flows outward through the opening. During the rated output operation, the lower end of the control rod 5 of the control rod cluster 1 is
0 is within the upper end.

【0005】[0005]

【発明が解決しようとする課題】上述するように、案内
管構造体35の中には、原子炉冷却材が流れているか
ら、この中に垂下保持されれている細い制御棒5は、流
体誘起振動を受け、振動しやすい。このようにして振動
する制御棒5は、案内管構造体35内では案内支持部
に、燃料集合体20内では案内シンブル25の内面にそ
れぞれ接触して摩耗が生じ、進行する。このような摩耗
の発生、進行は、最悪の場合には制御棒5の被覆管7の
貫通損傷となることもあるから、損傷が発生しやすい被
覆管7の外面に、クロムメッキなどのコーティング(図
7参照)を施している。更には、制御棒5の被覆管7の
下部のクロムメッキは、案内シンブル25の下部に形成
されるダッシュポット部との干渉を少なくするために厚
さを少なくする等、厚さにも適宜変化をつけている。
As described above, since the reactor coolant flows in the guide tube structure 35, the thin control rod 5 suspended and held in the guide tube structure 35 Subject to induced vibration, easily vibrates. The control rod 5 oscillating in this way contacts the guide support portion in the guide tube structure 35 and the inner surface of the guide thimble 25 in the fuel assembly 20 to be worn and progress. In the worst case, the occurrence and progress of such abrasion may result in the penetration of the cladding tube 7 of the control rod 5. Therefore, the outer surface of the cladding tube 7, which is liable to be damaged, is coated with chrome plating or the like. (See FIG. 7). Further, the thickness of the chrome plating on the lower part of the cladding tube 7 of the control rod 5 is appropriately changed, for example, the thickness is reduced in order to reduce interference with a dash pot formed on the lower part of the guide thimble 25. Is attached.

【0006】以上のようなクロムメッキなどのコーティ
ングは、従来制御棒5を組み立てる前に、被覆管7単体
の状態乃至は被覆管7と上部端栓9を溶接した後の状態
で施していたが、この方法だと、下部端栓11と被覆管
7との溶接部までコーティングを施すことができない。
このため、下部端栓11と被覆管7との溶接部付近に、
一部分、耐摩耗性の向上が付与されていない部分が残る
ことがある。又、制御棒5を組み立てるに当たり、被覆
管7と下部端栓11を溶接した後にコーティングを施し
たとしても、上部端栓9と被覆管7との溶接部の付近に
一部分、耐摩耗性が付与されていない部分が残ることと
なる。従って、本発明の課題は、制御棒の製作に際し、
被覆管7とその両端の溶接部を含め、その外面に残り無
くコーティングを施すことのできる加圧水型原子炉用制
御棒の製造方法を提供するとである。
Conventionally, coating such as chrome plating as described above has been applied before the control rod 5 is assembled, either in the state of the cladding tube 7 alone or after the cladding tube 7 and the upper end plug 9 are welded. According to this method, coating cannot be applied to the welded portion between the lower end plug 11 and the cladding tube 7.
For this reason, near the weld between the lower end plug 11 and the cladding tube 7,
In some cases, a portion to which no improvement in wear resistance has been imparted may remain. In addition, when the control rod 5 is assembled, even if the coating is applied after the cladding tube 7 and the lower end plug 11 are welded, abrasion resistance is partially provided near the welded portion between the upper end plug 9 and the cladding tube 7. The part which is not done will remain. Therefore, an object of the present invention is to manufacture a control rod,
It is an object of the present invention to provide a method for manufacturing a control rod for a pressurized water reactor, which can coat the outer surface including the cladding tube 7 and the welds at both ends thereof without any residue.

【0007】[0007]

【課題を解決するための手段】前記課題を解決するた
め、本発明によれば、被覆管、同被覆管の上端と下端に
それぞれ接合される上部端栓と下部端栓、及び前記被覆
管内に入れられる中性子吸収材とばねから構成される制
御棒を製造する基本的工程は次の手順に従って行われ
る。即ち被覆管の上端又は下端に上部端栓又は下部端栓
を第1の溶接又は第2の溶接により接合固定し、しかる
後、前記被覆管の中に前記中性子吸収材及び前記ばねを
挿入し、最後に被覆管の下端又は上端に下部端栓又は上
部端栓を第2の溶接又は第1の溶接により接合固定す
る。そして、被覆管の外周面のコーティングは、第1又
は第2の溶接の内最初に行われる溶接の領域の外周部と
共に第1のコーティングとして行われる。後から行われ
る溶接の領域の外周部のコーティングは、第2のコーテ
ィングとして行われ、下部端栓の外周面のコーティング
は、被覆管と下部端栓との間の前記第2の溶接の領域の
コーティングと共に行われる。尚、被覆管の外周面のコ
ーティングは、被覆管単体のときに行っても良い。
According to the present invention, there is provided, in accordance with the present invention, a cladding tube, an upper end plug and a lower end plug respectively joined to an upper end and a lower end of the cladding tube, and The basic process of manufacturing a control rod composed of a neutron absorber and a spring to be put in is performed according to the following procedure. That is, the upper end plug or the lower end plug is fixedly joined to the upper end or lower end of the cladding tube by the first welding or the second welding, and thereafter, the neutron absorbing material and the spring are inserted into the cladding tube, Finally, a lower end plug or an upper end plug is joined and fixed to the lower end or the upper end of the cladding tube by the second welding or the first welding. Then, the coating on the outer peripheral surface of the cladding tube is performed as the first coating together with the outer peripheral portion of the region of the first or second welding performed in the first welding. The coating of the outer periphery of the region of the welding to be performed later is performed as a second coating, and the coating of the outer peripheral surface of the lower end plug is formed in the region of the second welding between the cladding tube and the lower end plug. Performed with coating. The coating of the outer peripheral surface of the cladding tube may be performed when the cladding tube is used alone.

【0008】[0008]

【発明の実施の形態】以下添付の図面を参照して本発明
の実施形態を説明する。尚、従来技術に関する図面を含
め、全図に亘り同一部分には同一の符号を付すこととす
る。先ず図1を参照するに、被覆管7を準備し(a)、
被覆管7の上端に上部端栓9を溶接41により接合固定
する(b)。次に、上部端栓9と被覆管7との溶接部の
周囲及び被覆管7の外周部にコーティング43を施す。
コーティング43としては、クロムメッキでよい。コー
ティング43は、従来のコーティングに相当する部分4
3aと延長部43bとからなるが、被覆管7の下部端栓
11との接合部にはコーティングが施されない(c)。
次に、被覆管7の中にばね15及び中性子吸収材13を
入れ、その後被覆管7と下部端栓11とを溶接45によ
り接合固定する(d)。最後に、下部端栓11の外周面
及び下部端栓11と被覆管7との溶接部の周囲に追加的
な表面コーティング47を施す(e)。このようにする
と、被覆管7及び下部端栓11の全外周面並びに上部端
栓9の溶接部の周囲は、コーティング43及び表面コー
ティング47により漏れなく覆われたことになり、制御
棒40が完成する(f)。
Embodiments of the present invention will be described below with reference to the accompanying drawings. Note that the same portions are denoted by the same reference numerals throughout the drawings, including the drawings related to the prior art. First, referring to FIG. 1, a cladding tube 7 is prepared (a),
The upper end plug 9 is joined and fixed to the upper end of the cladding tube 7 by welding 41 (b). Next, a coating 43 is applied around the welded portion between the upper end plug 9 and the cladding tube 7 and on the outer peripheral portion of the cladding tube 7.
The coating 43 may be chrome plating. The coating 43 is a part 4 corresponding to the conventional coating.
3a and the extension 43b, but no coating is applied to the joint between the cladding tube 7 and the lower end plug 11 (c).
Next, the spring 15 and the neutron absorbing material 13 are put into the cladding tube 7, and then the cladding tube 7 and the lower end plug 11 are joined and fixed by welding 45 (d). Finally, an additional surface coating 47 is applied to the outer peripheral surface of the lower end plug 11 and around the weld between the lower end plug 11 and the cladding tube 7 (e). In this way, the entire outer peripheral surface of the cladding tube 7 and the lower end plug 11 and the periphery of the welded portion of the upper end plug 9 are completely covered by the coating 43 and the surface coating 47, and the control rod 40 is completed. (F).

【0009】次に前記実施形態の改変例を図2を参照し
て説明する。異なる部分のみを説明すれば、工程cで行
うコーティングは従来施工部分43a即ち、ダッシュポ
ット対応部を除く分のみのとする。ダッシュポット対応
部のコーティングは、工程eにおいて、下部端栓11と
被覆管7の下部端栓11との接合部の表面コーティング
49に含めて行う。このようにして完成した制御棒は、
前記実施形態の場合と同様に制御棒40となる。表面コ
ーティング49の厚さは、ダッシュポット部への挿入性
を考慮して、コーティング43aより小さくするのが良
い。この実施形態において、コーティング生成は、コー
ティング43aと表面コーティング49の2つに分けて
行い、前者を先に行ったが、被覆管7と上部端栓9との
溶接及び下部端栓11との溶接の順序を逆にし、表面コ
ーティング49を先に行って、最後にコーティング43
aを行っても良い。
Next, a modification of the above embodiment will be described with reference to FIG. Explaining only the different part, the coating performed in the step c is only the part except the conventional construction part 43a, that is, the part corresponding to the dashpot. The coating of the dashpot-corresponding portion is performed in step e by including it in the surface coating 49 of the joint between the lower end plug 11 and the lower end plug 11 of the cladding tube 7. The control rod completed in this way is
The control rod 40 is the same as in the above embodiment. The thickness of the surface coating 49 is preferably smaller than that of the coating 43a in consideration of the insertability into the dash pot portion. In this embodiment, the coating is divided into the coating 43a and the surface coating 49, and the former is performed first, but the welding of the cladding tube 7 and the upper end plug 9 and the welding of the lower end plug 11 are performed. , The surface coating 49 is performed first, and finally the coating 43 is performed.
a may be performed.

【0010】次に本発明の別の実施形態を図3を参照し
て説明する。図3において、被覆管7を準備し(a)、
被覆管7の下端に下部端栓11を溶接45により接合固
定する(b)。次に、上部端栓9と被覆管7との溶接部
の周囲を除く被覆管7の外周面及び下部端栓11との溶
接部45の外周面にコーティング51を施す。コーティ
ング51としては、クロムメッキでよい(c)。次に、
被覆管7の中にばね15及び中性子吸収材13を入れ、
その後被覆管7と上部端栓9とを溶接41により接合固
定する(d)。最後に、上部端栓9と被覆管7との溶接
部の周囲に追加的な表面コーティング53を施す
(e)。表面コーティング53は、必要により2段コー
ティングとすれば、耐摩耗性は向上する。このようにす
ると、被覆管7及び下部端栓11の全外周面並びに上部
端栓9の溶接部の周囲は、コーティング51及び表面コ
ーティング53により漏れなく覆われたことになり、制
御棒50が完成する(f)。
Next, another embodiment of the present invention will be described with reference to FIG. In FIG. 3, a cladding tube 7 is prepared (a),
The lower end plug 11 is joined and fixed to the lower end of the cladding tube 7 by welding 45 (b). Next, a coating 51 is applied to the outer peripheral surface of the cladding tube 7 excluding the periphery of the welded portion between the upper end plug 9 and the clad tube 7 and the outer peripheral surface of the welded portion 45 to the lower end plug 11. The coating 51 may be chrome plating (c). next,
A spring 15 and a neutron absorbing material 13 are put in the cladding tube 7,
Thereafter, the cladding tube 7 and the upper end plug 9 are joined and fixed by welding 41 (d). Finally, an additional surface coating 53 is applied around the weld between the upper end plug 9 and the cladding tube 7 (e). If the surface coating 53 is a two-stage coating as required, the abrasion resistance is improved. In this way, the entire outer peripheral surface of the cladding tube 7 and the lower end plug 11 and the periphery of the welded portion of the upper end plug 9 are completely covered with the coating 51 and the surface coating 53, and the control rod 50 is completed. (F).

【0011】次に本発明の更に別の実施形態を図4を参
照して説明する。図4において、被覆管7を準備し
(a)、被覆管7が単体の状態で外周面にコーティング
61を施す(b)。コーティング61としては、クロム
メッキでよいが、両端の予定溶接部の外周面はコーティ
ングをしない。次に被覆管7の上端に上部端栓9を溶接
41により接合固定し、更に被覆管7の中にばね15及
び中性子吸収材13を入れる(c)。その後被覆管7と
下部端栓11とを溶接45により接合固定する(d)。
最後に、上部端栓9と被覆管7との溶接41の周囲、下
部端栓11と被覆管7との溶接45及び下部端栓11の
外周面に追加コーティング63、65をそれぞれ施す
(e)。このようにすると、被覆管7及び下部端栓11
の全外周面並びに上部端栓9の溶接部の周囲は、コーテ
ィング61及び追加コーティング63、65により漏れ
なく覆われたことになり、制御棒60が完成する
(f)。
Next, still another embodiment of the present invention will be described with reference to FIG. In FIG. 4, a cladding tube 7 is prepared (a), and a coating 61 is applied to the outer peripheral surface of the cladding tube 7 alone (b). As the coating 61, chrome plating may be used, but the outer peripheral surfaces of the scheduled welds at both ends are not coated. Next, the upper end plug 9 is fixed to the upper end of the cladding tube 7 by welding 41, and a spring 15 and a neutron absorbing material 13 are put into the cladding tube 7 (c). Thereafter, the cladding tube 7 and the lower end plug 11 are joined and fixed by welding 45 (d).
Finally, additional coatings 63 and 65 are applied around the weld 41 between the upper end plug 9 and the cladding tube 7, the weld 45 between the lower end plug 11 and the cladding tube 7, and the outer peripheral surface of the lower end plug 11 (e). . By doing so, the cladding tube 7 and the lower end plug 11
Is completely covered by the coating 61 and the additional coatings 63 and 65, and the control rod 60 is completed (f).

【0012】[0012]

【発明の効果】以上説明したように、本発明によれば、
制御棒が使用時に制御棒クラスタ案内管構造体及び燃料
集合体の案内シンブルに接触する可能性のある被覆管、
上部端栓及び下部端栓の外周面は溶接部も含め漏れなく
クロムメッキなどのコーティングが施されるので、摩耗
の発生、進展が抑制され、その使用寿命が増大される。
As described above, according to the present invention,
Cladding in which the control rods may contact the control rod cluster guide tube structure and the fuel assembly guide thimbles during use;
Since the outer peripheral surfaces of the upper end plug and the lower end plug, including the welded portion, are coated with chrome plating or the like without leakage, the occurrence and progress of abrasion are suppressed, and the service life thereof is increased.

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

【図1】本発明の実施形態に係る方法の工程図である。FIG. 1 is a process diagram of a method according to an embodiment of the present invention.

【図2】図1の実施形態に係る方法の一部を改変した改
変方法の工程図である。
FIG. 2 is a process diagram of a modification method in which a part of the method according to the embodiment of FIG. 1 is modified.

【図3】本発明の別の実施形態に係る方法の工程図であ
る。
FIG. 3 is a process diagram of a method according to another embodiment of the present invention.

【図4】本発明の更に別の実施形態に係る方法の工程図
である。
FIG. 4 is a process chart of a method according to still another embodiment of the present invention.

【図5】本発明が適用される制御棒が使用される状態の
制御棒クラスタを示す短縮立面図である。
FIG. 5 is a shortened elevational view showing a control rod cluster in a state where a control rod to which the present invention is applied is used.

【図6】従来の制御棒の構造を示す概略立断面図であ
る。
FIG. 6 is a schematic vertical sectional view showing the structure of a conventional control rod.

【図7】図6のVII−VII線に沿う拡大平断面図である。FIG. 7 is an enlarged plan sectional view taken along line VII-VII in FIG. 6;

【図8】本発明の制御棒が一緒に使用される燃料集合体
の一部切り欠き斜視図である。
FIG. 8 is a partially cutaway perspective view of a fuel assembly with which the control rod of the present invention is used.

【図9】本発明の制御棒が一緒に使用される制御棒クラ
スタ案内管構造体の概念図である。
FIG. 9 is a conceptual diagram of a control rod cluster guide tube structure used together with the control rod of the present invention.

【図10】図9の一部を拡大して示す部分拡大立面図で
ある。
10 is a partially enlarged elevation view showing a part of FIG. 9 in an enlarged manner.

【図11】図10のXI−XI線に沿う平断面図である。11 is a plan sectional view taken along line XI-XI in FIG.

【符号の説明】[Explanation of symbols]

7 被覆管 9 上部端栓 11 下部端栓 13 中性子吸収材 15 ばね 40 制御棒 41 溶接 43 コーティング 45 溶接 47 表面コーティング 7 Clad tube 9 Upper end plug 11 Lower end plug 13 Neutron absorbing material 15 Spring 40 Control rod 41 Welding 43 Coating 45 Welding 47 Surface coating

Claims (4)

【特許請求の範囲】[Claims] 【請求項1】 被覆管、同被覆管の上端と下端にそれぞ
れ接合される上部端栓と下部端栓、及び前記被覆管内に
入れられる中性子吸収材とばねから構成される制御棒を
製造するに際し、前記被覆管に前記上部端栓を第1の溶
接により接合固定し、前記第1の溶接の外周面及び前記
被覆管の外周面に第1のコーティングを施し、前記被覆
管の中に前記中性子吸収材及び前記ばねを挿入した後第
2の溶接により前記被覆管と前記下部端栓とを接合固定
し、しかる後前記下部端栓の外周面及び第2の溶接の外
周面に第2のコーティングを施す工程を経て組み立てる
ことを特徴とする加圧水型原子炉用制御棒の製造方法。
1. A control rod comprising a cladding tube, an upper end plug and a lower end plug respectively joined to an upper end and a lower end of the cladding tube, and a neutron absorbing material and a spring to be put in the cladding tube. Fixing the upper end plug to the cladding tube by first welding, applying a first coating to an outer peripheral surface of the first welding and an outer peripheral surface of the cladding tube, and placing the neutron in the cladding tube. After inserting the absorber and the spring, the cladding tube and the lower end plug are joined and fixed by second welding, and then a second coating is applied to the outer peripheral surface of the lower end plug and the outer peripheral surface of the second weld. A method for manufacturing a control rod for a pressurized water reactor, comprising the steps of:
【請求項2】 前記第2の溶接に近い前記被覆管の外周
面のコーティングを、前記第2のコーティングに含めて
施すことを特徴とする請求項1記載の加圧水型原子炉用
制御棒の製造方法。
2. The control rod for a pressurized water reactor according to claim 1, wherein a coating on an outer peripheral surface of the cladding tube close to the second welding is included in the second coating. Method.
【請求項3】 被覆管、同被覆管の上端と下端にそれぞ
れ接合される上部端栓と下部端栓、及び前記被覆管内に
入れられる中性子吸収材とばねから構成される制御棒を
製造するに際し、前記被覆管と前記下部端栓とを第1の
溶接により接合固定した後、前記被覆管の外周面、前記
下部端栓の外周面及び前記第1の溶接の外周面に第1の
コーティングを施し、前記被覆管の中に前記中性子吸収
材及び前記ばねを挿入した後第2の溶接により前記被覆
管と前記上部端栓とを接合固定し、しかる後前記第2の
溶接の外周面に第2のコーティングを施す工程を経て組
み立てることを特徴とする加圧水型原子炉用制御棒の製
造方法。
3. A method for manufacturing a cladding tube, an upper end plug and a lower end plug respectively joined to an upper end and a lower end of the cladding tube, and a control rod composed of a neutron absorbing material and a spring put in the cladding tube. After the cladding tube and the lower end plug are joined and fixed by a first welding, a first coating is applied to an outer peripheral surface of the cladding tube, an outer peripheral surface of the lower end plug, and an outer peripheral surface of the first welding. After inserting the neutron absorbing material and the spring into the cladding tube, the cladding tube and the upper end plug are joined and fixed by a second welding, and then a second welding is performed on the outer peripheral surface of the second welding. 2. A method for manufacturing a control rod for a pressurized water reactor, comprising: assembling through a step of applying a coating.
【請求項4】 被覆管、同被覆管の上端と下端にそれぞ
れ接合される上部端栓と下部端栓、及び前記被覆管内に
入れられる中性子吸収材とばねから構成される制御棒を
製造するに際し、前記被覆管の外周面に両端の溶接予定
近傍部を除いて第1のコーティングを施し、前記被覆管
に前記上部端栓を第1の溶接により接合固定し、前記被
覆管の中に前記中性子吸収材及び前記ばねを挿入した後
第2の溶接により前記被覆管と前記下部端栓とを接合固
定し、しかる後前記下部端栓の外周面、前記第2の溶接
の外周面及び前記第1の溶接の外周面に第2のコーティ
ングを施す工程を経て組み立てることを特徴とする加圧
水型原子炉用制御棒の製造方法。
4. A method for manufacturing a cladding tube, an upper end plug and a lower end plug respectively joined to an upper end and a lower end of the cladding tube, and a control rod comprising a neutron absorbing material and a spring to be put in the cladding tube. A first coating is applied to the outer peripheral surface of the cladding tube except for portions near both ends to be welded, and the upper end plug is joined and fixed to the cladding tube by first welding, and the neutron is inserted into the cladding tube. After inserting the absorber and the spring, the cladding tube and the lower end plug are joined and fixed by second welding, and then the outer peripheral surface of the lower end plug, the outer peripheral surface of the second welding, and the first A method for manufacturing a control rod for a pressurized water reactor, comprising: assembling through a step of applying a second coating to the outer peripheral surface of the welding of (1).
JP2000365706A 2000-11-30 2000-11-30 Method of manufacturing control rod for pressurized water reactor Pending JP2002168983A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2000365706A JP2002168983A (en) 2000-11-30 2000-11-30 Method of manufacturing control rod for pressurized water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2000365706A JP2002168983A (en) 2000-11-30 2000-11-30 Method of manufacturing control rod for pressurized water reactor

Publications (1)

Publication Number Publication Date
JP2002168983A true JP2002168983A (en) 2002-06-14

Family

ID=18836428

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2000365706A Pending JP2002168983A (en) 2000-11-30 2000-11-30 Method of manufacturing control rod for pressurized water reactor

Country Status (1)

Country Link
JP (1) JP2002168983A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2007298354A (en) * 2006-04-28 2007-11-15 Nuclear Fuel Ind Ltd Control rod for pressurized water reactor
CN109473190A (en) * 2018-11-29 2019-03-15 上海核工程研究设计院有限公司 A kind of secondary neutron source rod reducing tritium discharge

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2007298354A (en) * 2006-04-28 2007-11-15 Nuclear Fuel Ind Ltd Control rod for pressurized water reactor
CN109473190A (en) * 2018-11-29 2019-03-15 上海核工程研究设计院有限公司 A kind of secondary neutron source rod reducing tritium discharge

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