JPH0142397B2 - - Google Patents

Info

Publication number
JPH0142397B2
JPH0142397B2 JP57058170A JP5817082A JPH0142397B2 JP H0142397 B2 JPH0142397 B2 JP H0142397B2 JP 57058170 A JP57058170 A JP 57058170A JP 5817082 A JP5817082 A JP 5817082A JP H0142397 B2 JPH0142397 B2 JP H0142397B2
Authority
JP
Japan
Prior art keywords
collar
upper extension
pressure tube
pressure
extension pipe
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.)
Expired
Application number
JP57058170A
Other languages
Japanese (ja)
Other versions
JPS58176573A (en
Inventor
Hidenori Doge
Isao Oguchi
Kenichi Suzuki
Tsugio Oyamada
Kazuo Koga
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 JP57058170A priority Critical patent/JPS58176573A/en
Publication of JPS58176573A publication Critical patent/JPS58176573A/en
Publication of JPH0142397B2 publication Critical patent/JPH0142397B2/ja
Granted 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
    • 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

  • Sealing Battery Cases Or Jackets (AREA)
  • Rigid Pipes And Flexible Pipes (AREA)
  • Sealing Material Composition (AREA)
  • Joints Allowing Movement (AREA)

Description

【発明の詳細な説明】 本発明は、圧力管型原子炉の圧力管集合体上部
延長管部炭酸ガスシール部構造に係り、特に圧力
管集合体の保守、補修に好適な炭酸ガスシールベ
ローズと圧力管上部延長管との溶接継手構造に関
する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a structure of a carbon dioxide gas seal part of an upper extension pipe of a pressure tube assembly of a pressure tube nuclear reactor, and in particular to a carbon dioxide gas seal bellows suitable for maintenance and repair of the pressure tube assembly. This article relates to a welded joint structure between a pressure pipe and an upper extension pipe.

第1図に圧力管型原子炉を示す。 Figure 1 shows a pressure tube reactor.

本原子炉は、減速材である重水を保有するカラ
ンドリアタンク1、放射線、熱を遮へいする鉄水
しやへい体2、核燃料、冷却材である軽水を保有
しカランドリアタンク1の上、下を接続したカラ
ンドリア管9及び鉄水しやへい体2を貫通して格
子状に林立する圧力管集合体3より構成されてい
る。なお、圧力管集合体3は、鉄水しやへい体2
より突き出している鉄水スリーブ4のフランジタ
イプの先端部に支持ボルト5により支持(固定)
され、上部は自由にスライド可能である。
This reactor consists of a calandria tank 1 that holds heavy water as a moderator, an iron water shield 2 that shields radiation and heat, and the upper and lower parts of the calandria tank 1 that holds nuclear fuel and light water that is a coolant. It is composed of a calandria tube 9 connected to the pressure tubes 9 and a pressure tube assembly 3 that passes through the iron water shield body 2 and stands in a lattice shape. In addition, the pressure pipe assembly 3 is made of iron water shield body 2.
Supported (fixed) by a support bolt 5 at the tip of the flange type of the iron water sleeve 4 that protrudes further.
and the upper part can be freely slid.

また、前記支持点(固定点)より下方に延びて
いる下部延長管6には、冷却材である軽水を給水
するための入口管7が接続されている。ここで、
圧力管集合体3は、炉心にあつて燃料集合体を内
包する圧力管及びその上下に接続されるステンレ
ス鋼製の圧力管上部及び下部延長管8,6より構
成されており、一次冷却材(軽水)を内部流体、
熱絶縁ガス(炭酸ガス)を外部流体とする長尺管
状容器である。なお、炭酸ガスは高温の圧力管集
合体3から重水減速材への伝熱量を低減し、炭酸
ガス中の湿分を測定することにより、圧力管集合
体3、カランドリア管9からの漏洩を検知し、さ
らに圧力管カランドリア管9の腐食低減のため
に、両者間アニユラスを低湿度に維持することを
目的として流されている。
Further, an inlet pipe 7 for supplying light water, which is a coolant, is connected to the lower extension pipe 6 extending below the support point (fixed point). here,
The pressure tube assembly 3 is composed of a pressure tube containing the fuel assembly in the reactor core, and stainless steel upper and lower pressure tube extension tubes 8 and 6 connected above and below the pressure tube, and is used to carry the primary coolant ( light water) as internal fluid,
It is a long tubular container that uses thermally insulating gas (carbon dioxide gas) as the external fluid. Note that carbon dioxide gas reduces the amount of heat transferred from the high-temperature pressure pipe assembly 3 to the heavy water moderator, and leakage from the pressure pipe assembly 3 and calandria tube 9 is detected by measuring the moisture in the carbon dioxide gas. Furthermore, in order to reduce corrosion of the pressure tube calandria tube 9, the annulus between the two is kept at low humidity.

第2図及び第3図は第1図のA部詳細図を示す
もので、これは従来の上部炭酸ガスシール部構造
を示している。圧力管集合体3の下部支持部は固
定されているが、上部は熱膨張により自由に伸び
るため、圧力管集合体3の熱膨張を吸収でき、か
つ炭酸ガスの漏洩を抑制するため、軸方向に伸縮
可能なシールベローズ(溶接ベローズ)11を設
置している。ベローズ11はスリーブ15,14
及びつば13と接合している。
FIGS. 2 and 3 are detailed views of section A in FIG. 1, which shows the conventional upper carbon dioxide gas seal structure. The lower support part of the pressure tube assembly 3 is fixed, but the upper part freely expands due to thermal expansion, so that it can absorb the thermal expansion of the pressure tube assembly 3 and suppress the leakage of carbon dioxide gas. A seal bellows (welded bellows) 11 that can be expanded and contracted is installed. Bellows 11 has sleeves 15 and 14
and the collar 13.

また、つば13はベローズ保護管12及び上部
延長管8と溶接接合している。上部延長管8の熱
膨張に伴ない、つば13を介して保護管12が上
下方向にスライドする。さらに、圧力管集合体3
の圧力管と、上、下部延長管8,6の接続部の健
全性向上及びシールベローズ11保護のために、
一次冷却水出入口管からの配管反力によるねじり
モーメントが伝わらない構造として、保護管12
に設けられた切欠部とスリーブ15に設けられた
溝部に合わせて回り止めのコマ10が一ケ所(も
しくは2ケ所以上)に設置されている。
Further, the collar 13 is welded to the bellows protection tube 12 and the upper extension tube 8. As the upper extension tube 8 thermally expands, the protection tube 12 slides vertically via the collar 13. Furthermore, the pressure tube assembly 3
In order to improve the integrity of the connection between the pressure pipe and the upper and lower extension pipes 8 and 6 and protect the seal bellows 11,
The protection pipe 12 has a structure that prevents the torsional moment due to the piping reaction force from the primary cooling water inlet and outlet pipes from being transmitted.
A rotation stopper 10 is installed at one location (or two or more locations) in accordance with the notch provided in the sleeve 15 and the groove provided in the sleeve 15.

ここで、万一圧力管集合体3を交換しなければ
ならないような事態が生じた場合、上部延長管8
とつば13との溶接部16をグラインダ等によ
り、B部に示す範囲程度で削り取る必要がある。
しかしながら、上部延長管8に溶融した溶材を完
全に取り去るには、B部に示す範囲のみを取り除
くことだけでは困難であるために少なくともC部
に示す範囲のように削り取らなければならないと
考えられ、圧力管集合体3交換後、つば13に再
度開先を取つて溶接する事ができなくなる可能性
があると考えられる。
If a situation arises in which the pressure pipe assembly 3 must be replaced, the upper extension pipe 8
It is necessary to scrape off the welded portion 16 between the flange 13 and the flange 13 using a grinder or the like within the range shown in section B.
However, in order to completely remove the melted metal from the upper extension tube 8, it is difficult to remove only the area shown in part B, so it is thought that at least the area shown in part C must be scraped off. It is considered that after replacing the pressure tube assembly 3, there is a possibility that the collar 13 may not be able to be grooved and welded again.

この場合、スリーブ15とスリーブ14の溶接
部17を切離し、シールベローズ機構を取り外し
て、新しくシールベローズ機構を取り付け再溶接
しなければならなくなるという事態を生ずること
も予想される。
In this case, it is expected that a situation will arise in which the welded portion 17 of the sleeve 15 and the sleeve 14 must be separated, the seal bellows mechanism removed, and a new seal bellows mechanism attached and rewelded.

本発明の目的は、万一の場合の圧力管集合体3
交換作業に伴なう上部延長管部シール部構造と上
部延長管との接合部16の切離し作業を簡易化
し、シールベローズ部を交換することなく再利用
を可能にするシール部構造を提供することにあ
る。
The purpose of the present invention is to provide a pressure pipe assembly 3 in case of emergency.
To provide a seal part structure that simplifies the work of separating the joint part 16 between the upper extension pipe part seal part structure and the upper extension pipe during replacement work, and enables reuse without replacing the seal bellows part. It is in.

本発明では、上部延長管部シール部構造の上部
延長管との接合部を2段階溶接可能構造にするこ
とにより、シール部構造の補修性向上及びシール
ベローズの再利用を計るものである。
The present invention aims to improve the repairability of the seal structure and reuse the seal bellows by creating a two-step weldable structure for the joint portion of the upper extension tube seal structure with the upper extension tube.

以下、本発明の一実施例を第4図、第5図によ
り説明する。同図における第1図〜第3図と同符
号は同一部品を示している。
An embodiment of the present invention will be described below with reference to FIGS. 4 and 5. The same reference numerals as in FIGS. 1 to 3 indicate the same parts.

つば13は、径を小さくして軸方向に伸ばし、
開先を2ケ所に設けて、2段階溶接可能方式とし
ている。建設時に、つば13と上記延長管8との
接合部18を溶接する。次に圧力管集合体3を交
換する必要が生じた場合には、つば13をD―D
で切断した後、接合部18をグラインダ等で削り
取り、さらに圧力管を交換した後、第5図に示す
ように、接合部19を溶接する。
The collar 13 has a reduced diameter and extends in the axial direction.
Grooves are provided in two locations to enable two-step welding. During construction, the joint 18 between the collar 13 and the extension pipe 8 is welded. Next, if it becomes necessary to replace the pressure tube assembly 3, replace the collar 13 with D-D.
After cutting the joint 18 with a grinder or the like, and replacing the pressure pipe, the joint 19 is welded as shown in FIG.

従来の構造では、圧力管交換時にシールベロー
ズ部構造も同時に交換する必要があると考えられ
るが、本実施例では、交換の必要がなくシールベ
ローズを再利用できる。また、つば13の径を小
さくして軸方向に伸ばしたことにより切断作業が
容易になり、かつ溶接部18の除去作業も容易に
なる。
In the conventional structure, it would be necessary to replace the seal bellows structure at the same time when replacing the pressure pipe, but in this embodiment, there is no need for replacement and the seal bellows can be reused. Further, by reducing the diameter of the collar 13 and extending it in the axial direction, cutting work becomes easier, and the work of removing the welded portion 18 becomes easier.

なお、本実施例では2段階溶接方式を採用して
いるが、必要により3段階以上に拡張することも
可能である。
In this embodiment, a two-stage welding method is adopted, but it is also possible to extend the welding process to three or more stages if necessary.

本発明によれば、シールベローズ部と上部延長
管との溶接継手部の取外し及び再取付けが容易に
なり、さらにシールベローズ部を再利用でき、上
部延長管部炭酸ガスシール部構造の補修性を向上
させる効果がある。
According to the present invention, the welded joint between the seal bellows part and the upper extension pipe can be easily removed and reattached, the seal bellows part can be reused, and the repairability of the carbon dioxide seal part structure of the upper extension pipe part can be improved. It has the effect of improving

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

第1図は、圧力管型原子炉の全体概略断面図、
第2図は第1図のA部詳細図、第3図は、第2図
のE―E断面図、第4図は本発明による第3図と
同じ位置の断面図、第5図は再溶接状態を示す断
面図である。 3……圧力管集合体、11……シールベロー
ズ、13……つば、18……接合部、19……接
合部。
Figure 1 is an overall schematic sectional view of a pressure tube reactor;
Fig. 2 is a detailed view of part A in Fig. 1, Fig. 3 is a sectional view taken along line EE in Fig. 2, Fig. 4 is a sectional view of the same position as Fig. 3 according to the present invention, and Fig. 5 is a re-illustration. It is a sectional view showing a welding state. 3...Pressure tube assembly, 11...Seal bellows, 13...Brim, 18...Joint part, 19...Joint part.

Claims (1)

【特許請求の範囲】[Claims] 1 圧力管集合体の上部延長管に溶接にて固着さ
れるつばと、前記つばに連設されるベローズを前
記延長管周囲のガスシールの構成部材として備え
る圧力管型原子炉において、前記つばは他部より
も薄くして軸方向へ延長された部分を備え、且つ
軸方向に間隔を置いて前記上部延長管に対する溶
接開先を複数備え、前記複数の溶接開先の内少な
くとも一つは前記延長された部分に備わることを
特徴とした上部延長管部炭酸ガスシール部構造。
1. In a pressure tube nuclear reactor comprising a collar fixed to an upper extension pipe of a pressure tube assembly by welding, and a bellows connected to the collar as constituent members of a gas seal around the extension pipe, the collar is a portion that is thinner than other portions and extends in the axial direction, and a plurality of weld grooves for the upper extension tube that are spaced apart in the axial direction, and at least one of the plurality of weld grooves is The carbon dioxide gas seal structure of the upper extension pipe is characterized by being provided in the extended part.
JP57058170A 1982-04-09 1982-04-09 Upper extension pipe carbon dioxide seal structure Granted JPS58176573A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57058170A JPS58176573A (en) 1982-04-09 1982-04-09 Upper extension pipe carbon dioxide seal structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57058170A JPS58176573A (en) 1982-04-09 1982-04-09 Upper extension pipe carbon dioxide seal structure

Publications (2)

Publication Number Publication Date
JPS58176573A JPS58176573A (en) 1983-10-17
JPH0142397B2 true JPH0142397B2 (en) 1989-09-12

Family

ID=13076519

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57058170A Granted JPS58176573A (en) 1982-04-09 1982-04-09 Upper extension pipe carbon dioxide seal structure

Country Status (1)

Country Link
JP (1) JPS58176573A (en)

Also Published As

Publication number Publication date
JPS58176573A (en) 1983-10-17

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