JPS6046489A - Pressure vessel for nuclear reactor - Google Patents

Pressure vessel for nuclear reactor

Info

Publication number
JPS6046489A
JPS6046489A JP58153227A JP15322783A JPS6046489A JP S6046489 A JPS6046489 A JP S6046489A JP 58153227 A JP58153227 A JP 58153227A JP 15322783 A JP15322783 A JP 15322783A JP S6046489 A JPS6046489 A JP S6046489A
Authority
JP
Japan
Prior art keywords
housing
pressure vessel
cylindrical sleeve
crd
reactor pressure
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
JP58153227A
Other languages
Japanese (ja)
Inventor
小嶋 淳一
孝一 黒沢
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 Ltd
Original Assignee
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 Ltd filed Critical Hitachi Ltd
Priority to JP58153227A priority Critical patent/JPS6046489A/en
Publication of JPS6046489A publication Critical patent/JPS6046489A/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

  • Pressure Vessels And Lids Thereof (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】 〔発明の利用分野〕 本発明は、原子炉圧力容器に係り、特にCB、Dハウジ
ング廻シの構造に関する。
DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a nuclear reactor pressure vessel, and particularly to the structure of a CB and D housing.

〔発明の背景〕[Background of the invention]

第1図に、従来構造のC几Dハウジング2廻シの構造を
示す。
FIG. 1 shows the structure of a conventional two-turn C/D housing.

第1図において、原子炉圧力容器下鏡1にCI(、Dハ
ウジング2が貫通しており、下鏡1内面には、CRDハ
ウジング2を支える円筒スリーブ3が溶接により設置さ
れている。CRDハウジング2と円筒スリーブ3との取
付部は、円筒スリーブ3上端内面に開先を設け、溶接さ
れている。
In FIG. 1, a CI (D) housing 2 passes through a reactor pressure vessel lower mirror 1, and a cylindrical sleeve 3 supporting a CRD housing 2 is installed on the inner surface of the lower mirror 1 by welding. 2 and the cylindrical sleeve 3 are welded together by providing a groove on the inner surface of the upper end of the cylindrical sleeve 3.

しかし、第1図に示す構造では、溶接部4が万が一破断
した様な場合、CRDハウジング2は落下する可能性が
あり、これらの万一の事象を想定し、CRDハウジング
2下には、第2図に示すようなCRDハウジングサポー
トが設置場れ、安全上の配慮がなされている。
However, in the structure shown in FIG. 1, if the welded part 4 were to break, there is a possibility that the CRD housing 2 would fall. A CRD housing support as shown in Figure 2 is installed in consideration of safety.

しかしながら、プラント定期点検時CILDハウジング
2に内蔵される制御棒駆動機構を点検する際、これらC
RDハウジングサポートの取付・取外しに多大の労力を
要していた。
However, when inspecting the control rod drive mechanism built in the CILD housing 2 during regular plant inspections, these C
It took a lot of effort to install and remove the RD housing support.

また、CRDハウジングサポートの加工作業において1
例えばグリッドプレート5は、弾力性のある薄板を使用
するため曲げ加工する場合、強度の高い材料を使用する
ために、作業工数を多く費ず傾向があった。
In addition, in the machining work of the CRD housing support, 1
For example, since the grid plate 5 uses a thin elastic plate, bending tends to require a large number of man-hours because a high-strength material is used.

〔発明の目的〕[Purpose of the invention]

本発明の目的は%CRDハウジング2の落下防止機構を
、原子炉圧力容器下鏡1部の内面に設け、以って、前述
したCRDの取付・取外し・保守作業性を改善し1作業
者の被曝量を低減するものである。
The object of the present invention is to provide a fall prevention mechanism for the CRD housing 2 on the inner surface of the lower mirror 1 of the reactor pressure vessel, thereby improving the ease of installation, removal, and maintenance of the CRD mentioned above, and for one operator to This reduces the amount of radiation exposure.

この目的を達成する為に、CRDハウジング2を上下2
分割型とし、上部CRDハウジング2の外周面を円筒ス
リーブ3上端円面の開先面において、突起構造を設けた
。これにより、従来技法に比し%CRDハウジ/グ2の
万一の場合の落下を。
In order to achieve this purpose, the CRD housing 2 is
The upper CRD housing 2 is of a split type, and a protrusion structure is provided on the outer peripheral surface of the upper CRD housing 2 at the bevel surface of the upper circular surface of the cylindrical sleeve 3. This reduces the chance of the CRD housing falling by 2% compared to conventional techniques.

防止するものである。It is intended to prevent

〔発明の概要〕[Summary of the invention]

従来は、第1図に示す様に、原子炉圧力容器下鏡部1の
貫通部に挿着されるCB、Dハウジング2と、下鏡部1
内面貫通部に位置する円筒スリーブ3との取付部は、先
ず円筒スリーブ3−上端内面に溶接の為の開先面を設け
、溶接されていた。
Conventionally, as shown in FIG.
The attachment part to the cylindrical sleeve 3 located at the inner surface penetration part was first welded by providing a groove surface for welding on the inner surface of the upper end of the cylindrical sleeve 3.

本発明の特徴は。The characteristics of the present invention are as follows.

■ CRDハウジング2の落下防止機構を原子炉圧力容
器下鏡1内に設ける。
(2) A mechanism to prevent the CRD housing 2 from falling is provided in the lower mirror 1 of the reactor pressure vessel.

■ CRDハウジング2の上部外周形状を突起を設けた
構造とする。
(2) The upper outer periphery of the CRD housing 2 has a structure with protrusions.

■ 円筒スリーブ3上端内面開先面と、CRDハウジン
グ2の突起面がCRDハウジング2の落下防止構造とな
っている。
(2) The grooved surface on the inner surface of the upper end of the cylindrical sleeve 3 and the protruding surface of the CRD housing 2 form a structure to prevent the CRD housing 2 from falling.

以上により、前記CHDハウジング2と円筒スリーブ3
の溶接部4において万が一破断が生じた様な場合におい
ても、CRDハウジング2を落下しない構造とすること
である。
As described above, the CHD housing 2 and the cylindrical sleeve 3
The object of the present invention is to provide a structure in which the CRD housing 2 will not fall even if a break occurs in the welded portion 4 of the housing.

〔発明の実施例〕[Embodiments of the invention]

次に本発明の実施例を図面によって説明する。 Next, embodiments of the present invention will be described with reference to the drawings.

本発明による適用例を第3図、第4図、第5図に示す。Application examples of the present invention are shown in FIGS. 3, 4, and 5.

本発明では先ず第3図に示す様に、従来CILDハウジ
ング2と円筒スリーブ3とを溶接するために設けた円筒
スリーブ3上端内面の開先部の開先面下端C−D面と、
第4図に示す様な溶接タイプCRDハウジング2のC−
E部とを一致するように加工しておく。次に第5図に示
す様に更に溶接を施仁すことにより万一溶接部4におい
て破断が生じた様な場合においても、CRDハウジング
2の落下防止を行なえる。
In the present invention, first, as shown in FIG. 3, the groove surface of the groove portion on the inner surface of the upper end of the cylindrical sleeve 3 provided for welding the conventional CILD housing 2 and the cylindrical sleeve 3, the lower end C-D surface,
C- of welded type CRD housing 2 as shown in Fig. 4.
Process it so that it matches the E part. Next, by performing further welding as shown in FIG. 5, even if a break occurs in the welded portion 4, the CRD housing 2 can be prevented from falling.

第6図に示す様な一体型CRDハウジングにお、ける適
用例を、第7図により説明する。
An application example of the integrated CRD housing as shown in FIG. 6 will be explained with reference to FIG. 7.

本発明は、原子炉圧力容器下鏡1貫通孔の下から挿入さ
れたCRDハウジング2において、第7図に示す様に、
従来、CHDハウジング2と円筒スリーブ3とを溶接す
るため設けられた円筒スリーブ3上端内面の開先面を利
用して、その溝部にCRDハウジング2を拡管し更に溶
接を施こすことによシ、万一溶接部4において破断が生
じた様な場合においても、CRDハウジング2の落下防
止が行なえるものである。
The present invention provides a CRD housing 2 inserted from below a through hole of a reactor pressure vessel lower mirror 1, as shown in FIG.
Conventionally, by using the beveled surface on the inner surface of the upper end of the cylindrical sleeve 3 provided for welding the CHD housing 2 and the cylindrical sleeve 3, the CRD housing 2 is expanded into the groove and further welding is performed. Even in the unlikely event that a break occurs in the welded portion 4, the CRD housing 2 can be prevented from falling.

〔発明の効果〕〔Effect of the invention〕

第6図、第9図に示す様に、CI(、Dハウジング2の
落下を、従来、CB、Dハウジング2と円筒スリーブ3
との溶接のために設けられた円筒スリーブ3上端内面の
開先面を利用して防止するため。
As shown in FIG. 6 and FIG.
To prevent this by utilizing the grooved surface on the inner surface of the upper end of the cylindrical sleeve 3 provided for welding with the cylindrical sleeve 3.

CHDハウジングサポートが不要となシ従来技術による
CRDハウジング2落下防止法と比し、C11,Dハウ
ジングサポートの定期点検時の取付・取外しが不要とな
る為大幅な作業性改善、被曝量低減が唱れる。
No need for CHD housing support Compared to the CRD housing 2 drop prevention method using conventional technology, it is no longer necessary to install and remove C11 and D housing supports during periodic inspections, resulting in significant improvements in workability and reduction in radiation exposure. It will be done.

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

第1図は制御棒駆動機構(CRD)ハウジングと円筒ス
リーブの従来型取付図、第2図は従来使用されているC
R,Dハウジングの支持サポート図、第3図は円筒スリ
ーブの上端内面の拡大図、第4図は溶接タイプ新規CR
Dハウジング図、第5図。 第7図は第1図のA部詳細図、第6図は一体型CRDハ
ウジングを示す図である。
Figure 1 is a conventional installation diagram of the control rod drive mechanism (CRD) housing and cylindrical sleeve, and Figure 2 is a conventional installation diagram of the control rod drive mechanism (CRD) housing and cylindrical sleeve.
Support diagram of R and D housings, Figure 3 is an enlarged view of the inner surface of the upper end of the cylindrical sleeve, Figure 4 is a welding type new CR
D housing diagram, Figure 5. FIG. 7 is a detailed view of part A in FIG. 1, and FIG. 6 is a view showing the integrated CRD housing.

Claims (1)

【特許請求の範囲】[Claims] 1、沸騰水型原子炉圧力容器の内面に取付けられた円筒
スリーブ内に、原子炉圧力容器の壁を貫通して挿入され
、前記円筒スリーブに溶接部で結合された制御棒駆動機
構ハウジング(以下CRDハウジングと略す。)におい
て、前記CB、Dハウジングに、落丁防止を目的とした
突起を設け、(JDハウジングと円筒スリーブとを溶接
する為に設けられていた円筒スリーブ上端内面の開先面
で支持することを特徴とする原子炉圧力容器。
1. A control rod drive mechanism housing (hereinafter referred to as "control rod drive mechanism housing") inserted into a cylindrical sleeve attached to the inner surface of the boiling water reactor pressure vessel through the wall of the reactor pressure vessel and connected to the cylindrical sleeve by a welded part. (abbreviated as CRD housing), the CB and D housings are provided with protrusions for the purpose of preventing falling pages, A nuclear reactor pressure vessel characterized by supporting.
JP58153227A 1983-08-24 1983-08-24 Pressure vessel for nuclear reactor Pending JPS6046489A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58153227A JPS6046489A (en) 1983-08-24 1983-08-24 Pressure vessel for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58153227A JPS6046489A (en) 1983-08-24 1983-08-24 Pressure vessel for nuclear reactor

Publications (1)

Publication Number Publication Date
JPS6046489A true JPS6046489A (en) 1985-03-13

Family

ID=15557832

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58153227A Pending JPS6046489A (en) 1983-08-24 1983-08-24 Pressure vessel for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS6046489A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2701785A1 (en) * 1993-02-19 1994-08-26 Framatome Sa Tubular penetration part for the vessel head of a nuclear reactor having dismountable thermal sleeve and inspection method
JP2014178288A (en) * 2013-03-15 2014-09-25 Hitachi-Ge Nuclear Energy Ltd Reactor containment vessel
JPWO2013150750A1 (en) * 2012-04-03 2015-12-17 株式会社東芝 Reactor pressure vessel penetration protection structure and reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2701785A1 (en) * 1993-02-19 1994-08-26 Framatome Sa Tubular penetration part for the vessel head of a nuclear reactor having dismountable thermal sleeve and inspection method
JPWO2013150750A1 (en) * 2012-04-03 2015-12-17 株式会社東芝 Reactor pressure vessel penetration protection structure and reactor
JP2014178288A (en) * 2013-03-15 2014-09-25 Hitachi-Ge Nuclear Energy Ltd Reactor containment vessel

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