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JPS608789A - Boiling water reactor pressure vessel with screwing type crdstub - Google Patents

Boiling water reactor pressure vessel with screwing type crdstub

Info

Publication number
JPS608789A
JPS608789A JP58116203A JP11620383A JPS608789A JP S608789 A JPS608789 A JP S608789A JP 58116203 A JP58116203 A JP 58116203A JP 11620383 A JP11620383 A JP 11620383A JP S608789 A JPS608789 A JP S608789A
Authority
JP
Japan
Prior art keywords
stub
crd
pressure vessel
reactor pressure
lower mirror
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
JP58116203A
Other languages
Japanese (ja)
Inventor
大下 正司
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 Power Ltd
Original Assignee
Babcock Hitachi 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 Babcock Hitachi KK filed Critical Babcock Hitachi KK
Priority to JP58116203A priority Critical patent/JPS608789A/en
Publication of JPS608789A publication Critical patent/JPS608789A/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

  • Physical Or Chemical Processes And Apparatus (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】 本発明は沸騰水形原子炉圧力容器に係り、符に容器(7
) 下’itA トCRD (CON TR0L uO
D−−ft1lJ ml棒)スタブの接続構造に関する
ものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a boiling water reactor pressure vessel.
) 下'itA トCRD (CON TR0L uO
D--ft1lJ ml rod) This relates to the connection structure of the stub.

まず第1図に従来例の、C1(、l)スタブと原子炉圧
力容器下鏡との接合部近傍の構造を示す。
First, FIG. 1 shows the structure of a conventional example near the joint between the C1 (, l) stub and the lower head of the reactor pressure vessel.

図において、1はCRDスタブであり、2は下鏡である
。このC)l、DスタブIKはCRDハウジング5が嵌
合されている。C1(、l)ハウジング5の内部には、
原子炉を制御するための重要な制御棒が挿入されており
、この為CRDスタブの取付精度は高いものが要求され
ている。
In the figure, 1 is a CRD stub, and 2 is a lower mirror. The CRD housing 5 is fitted into the C)l and D stubs IK. Inside the C1(,l) housing 5,
Important control rods for controlling the nuclear reactor are inserted, and for this reason, high precision CRD stub installation is required.

ところで今C’RDスタブ1を設けることなしに、CR
Dハウジング5を直接下鏡2に取り付けた場合を考えて
見る。この場合、内圧による影響が直接下鏡に及び(下
鏡の変形)、またCRDハウジング5内部には低温の制
御棒出動用冷却水が流れているので炉水温度に支配され
る下鏡2との間に温度差を生じて大きな応力が発生し、
下鏡2の強度上厳しいものとなる。
By the way, now without providing C'RD stub 1, CR
Let us consider the case where the D housing 5 is directly attached to the lower mirror 2. In this case, the lower mirror is directly affected by the internal pressure (deformation of the lower mirror), and since low-temperature control rod dispatch cooling water flows inside the CRD housing 5, the lower mirror 2 is affected by the reactor water temperature. A large stress is generated due to the temperature difference between the
This poses a severe problem in terms of the strength of the lower mirror 2.

これらt7)事情に゛より下鏡2とCRDハウジング5
との間には緩衝の役目全果たすCHDスタブ1が設けら
れているのである。
Due to these t7) circumstances, the lower mirror 2 and CRD housing 5
A CHD stub 1 is provided between the two and the CHD stub 1, which serves as a buffer.

従来のC几りスタブlと下鏡2との接合はどの様にして
行なわれていたかと言うと、図に示す様に溶着部3ff
:介して下鏡2に取り付けることによって行なわれてい
た。またCRDスタブ1上端には溶着部4を介してCR
Dハウジング5が取り付けられている。
The conventional way of joining the C-shaped stub l and the lower mirror 2 is as shown in the figure.
: This was done by attaching it to the lower mirror 2 via the mirror. In addition, the upper end of the CRD stub 1 has a CR
D housing 5 is attached.

そしてこれら浴着部3,4を形成するに際しては、溶着
量の多い完全溶は込み溶接法が用いられている。このた
め浴着部形成時の、山側と谷側の溶着量の差に基く溶接
変形量が大きく、18度の高いC几Dスタブ1の取り付
け、及び形状の保持のためには、特別の工夫をこらす必
要があり、製作性の悪いものとなっていた。
When forming these bath welding parts 3 and 4, a full penetration welding method is used which allows for a large amount of welding. For this reason, when forming the bath welding part, the amount of welding deformation due to the difference in the amount of welding on the peak side and the valley side is large, and special measures are required to install the C-D stub 1 with a high angle of 18 degrees and maintain the shape. This required a lot of effort, making it difficult to manufacture.

本発明は以上述べた従来例の欠点に鑑みてなされたもの
であり、、CR1)スタブの機能を損なうことなく製作
精度の高い沸臓水形原子炉圧力容器を提供することを目
的とするものである。
The present invention has been made in view of the above-mentioned drawbacks of the conventional examples, and an object of the present invention is to provide a boiling water reactor pressure vessel that can be manufactured with high precision without impairing the function of the CR1) stub. It is.

この目的を達成するために、本発明では、CRDスタブ
を下鏡にネジ込み、さらにCRDスタブと下鏡とのネジ
込み部にシール溶接を施したものである。
In order to achieve this object, in the present invention, the CRD stub is screwed into the lower mirror, and the threaded portion between the CRD stub and the lower mirror is seal-welded.

以下本発明を第2図、第3図に示す実施例に基づき説明
する。
The present invention will be explained below based on the embodiments shown in FIGS. 2 and 3.

尚、第1図に示す従来例と同一個所は同一符号と1−る
Note that the same parts as in the conventional example shown in FIG. 1 are designated by the same reference numerals.

まず第2図は第1実施例に係る要部縦断面図であるが、
この図から明らかな迎り、C几Dスタブ1の下部はネジ
部6になっている。また下鏡2についてもCit D貫
通孔部にネジ加工が施されて(・る。このことにより、
(1−tDスタブ1はネジ込み式で下鏡2に固定される
。CRDスタブlと下鏡2の接続部、特に下鏡2の端面
とC几Dスタブ1の外周部でなす隅部にはネジ込み後シ
ール溶接が行なわれ、これによりシール溶接s7を形成
する。
First, FIG. 2 is a longitudinal sectional view of the main part according to the first embodiment,
As is clear from this figure, the lower part of the C-D stub 1 is a threaded portion 6. Also, for the lower mirror 2, the Cit D through hole is threaded.
(1-tD stub 1 is fixed to the lower mirror 2 with a screw-in type. After screwing, seal welding is performed, thereby forming a seal weld s7.

尚、CRDスタブ1の上端には従前通り、溶着部4を介
してCRD〕・ウジング5が取り付けられる。
Note that a CRD housing 5 is attached to the upper end of the CRD stub 1 via a welded portion 4 as before.

本実施例によれは、CRDスタブ1と下鏡2と、の接続
部の強度は、ネジ部6で受け持つため、浴着量の多い完
全溶は込み溶接部(第1図の浴着部3)が不要となる。
According to this embodiment, the strength of the connection between the CRD stub 1 and the lower mirror 2 is provided by the threaded portion 6, so that the fully penetrated welded portion with a large amount of bath coat (bath coat portion 3 in FIG. ) becomes unnecessary.

この為、CRDスタブ1の、下鏡2に対する浴接変形が
なくなり、原子炉圧力容器の製作性及び製作稍度葡高め
る効果がある。
Therefore, deformation of the CRD stub 1 in contact with the lower mirror 2 is eliminated, which has the effect of improving the manufacturability and quality of the reactor pressure vessel.

第3図は第2実施例に係る第2図同様図であり、この実
施例では、C礼りヌタブ1は、下部及び上部にネジ加工
(ネジ部6.8)が施されている。
FIG. 3 is a view similar to FIG. 2 relating to the second embodiment, and in this embodiment, the C-shaped nut tab 1 is threaded (threaded portions 6.8) at the lower and upper portions.

C几Dスタブ1の下鏡2への固定方法は、第2図に示す
第1実施例と同様にネジ込み式であり、C托Oスタブと
下鏡との接続部にはシール溶接部7が形成される。C1
(Dスタブ1の上端は、下部と同様ネジ込み式でCRD
ハウジング5が取り付けられ、C几Dスタブ1とCRD
ハウジング5との接続部には冷却水漏洩防止のためにシ
ール溶接が行なわれ、シール溶接部9が形成される。
The method of fixing the C-type D stub 1 to the lower mirror 2 is a screw-in type similar to the first embodiment shown in FIG. is formed. C1
(The upper end of D stub 1 is a screw-in type like the lower part.
Housing 5 is installed, C-D stub 1 and CRD
Seal welding is performed at the connection with the housing 5 to prevent leakage of cooling water, and a seal weld 9 is formed.

本実施例によれば、ci(1)スタブ1と下鏡2及びC
RDハウジング5との接続部の強度はネジ部6.8で受
け持ち、第1実施例同様、溶着量の多い完全篩は込み溶
接部(第1図の溶着部3,4)が不要となる。この為、
CRDスタブ1の下鏡2に対する浴接変形がなくなると
同時に、CHI)スタブ1の板厚を薄く出来るという効
果がある。
According to this embodiment, ci(1) stub 1, lower mirror 2 and C
The strength of the connection with the RD housing 5 is provided by the threaded portion 6.8, and as in the first embodiment, the complete sieve welded portion (welded portions 3 and 4 in FIG. 1), which has a large amount of welded material, is not required. For this reason,
This has the effect of eliminating the bath contact deformation of the CRD stub 1 with respect to the lower mirror 2, and at the same time, making it possible to reduce the thickness of the CHI stub 1.

本発明は以上述べた通りのものであり、本発明によれは
、CRDスタブ會下銃に取り付けるための多量の溶着量
が不要となり、このためC几Dスタブの下鏡への取り伺
は時溶接変形がな(なる。
The present invention is as described above, and according to the present invention, a large amount of welding is not required for attaching the CRD stub to the lower gun, and therefore it is time consuming to inspect the lower mirror of the CRD stub. There is no welding deformation.

従ってC几りスタブQ)取付相変向上が可能となる。Therefore, it is possible to improve the installation phase change of the C-cut stub Q).

またネジ構造であることから、据付が容易となる。Also, since it has a screw structure, installation is easy.

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

第1図は従来例に係るCRDスタブと原子炉圧力容器下
鏡との接続部近傍の縦断面図、第2図は本発明の第1実
施例に係る第1図同様図、第3図は同第2実施例に係る
第1図同様図である。 l・・・・・・CB、Dスタブ、2・・・・・・下鏡、
5・・・・・・CRDハウジング、7,9・・・・・・
シール溶接部。
FIG. 1 is a vertical cross-sectional view of the vicinity of the connection between the CRD stub and the lower head of the reactor pressure vessel according to the conventional example, FIG. 2 is a view similar to FIG. 1 according to the first embodiment of the present invention, and FIG. It is a figure similar to FIG. 1 concerning the same 2nd Example. l...CB, D stub, 2...lower mirror,
5...CRD housing, 7,9...
Seal weld.

Claims (1)

【特許請求の範囲】[Claims] 内部にCRDハウジング?嵌合し、且つ原子炉圧力容器
の下鏡に螺合され、さらに下鏡との接続部にシール溶接
部を形成した(、RDスタブ全有することを特徴とする
ネジ込み弐CRDスタブを有する沸騰水形原子炉圧力容
器。
CRD housing inside? A boiler with two screwed CRD stubs is fitted and screwed onto the lower head of the reactor pressure vessel, and a seal weld is formed at the connection with the lower head (the boiler has a screw-in second CRD stub, which is characterized by having an entire RD stub). Water reactor pressure vessel.
JP58116203A 1983-06-29 1983-06-29 Boiling water reactor pressure vessel with screwing type crdstub Pending JPS608789A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58116203A JPS608789A (en) 1983-06-29 1983-06-29 Boiling water reactor pressure vessel with screwing type crdstub

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58116203A JPS608789A (en) 1983-06-29 1983-06-29 Boiling water reactor pressure vessel with screwing type crdstub

Publications (1)

Publication Number Publication Date
JPS608789A true JPS608789A (en) 1985-01-17

Family

ID=14681386

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58116203A Pending JPS608789A (en) 1983-06-29 1983-06-29 Boiling water reactor pressure vessel with screwing type crdstub

Country Status (1)

Country Link
JP (1) JPS608789A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2011145271A (en) * 2010-01-18 2011-07-28 Mitsubishi Heavy Ind Ltd Nozzle stub mounting structure
CZ306597B6 (en) * 2011-10-11 2017-03-22 Areva Gmbh A security device for a steering rod in a nuclear facility

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2011145271A (en) * 2010-01-18 2011-07-28 Mitsubishi Heavy Ind Ltd Nozzle stub mounting structure
US8867688B2 (en) 2010-01-18 2014-10-21 Mitsubishi Heavy Industries, Ltd. Nozzle mounting structure
CZ306597B6 (en) * 2011-10-11 2017-03-22 Areva Gmbh A security device for a steering rod in a nuclear facility

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