JPS6159290A - Fast breeder reactor - Google Patents

Fast breeder reactor

Info

Publication number
JPS6159290A
JPS6159290A JP59181837A JP18183784A JPS6159290A JP S6159290 A JPS6159290 A JP S6159290A JP 59181837 A JP59181837 A JP 59181837A JP 18183784 A JP18183784 A JP 18183784A JP S6159290 A JPS6159290 A JP S6159290A
Authority
JP
Japan
Prior art keywords
reactor vessel
skirt
reactor
thin
fast breeder
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
JP59181837A
Other languages
Japanese (ja)
Inventor
我妻 研自
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP59181837A priority Critical patent/JPS6159290A/en
Publication of JPS6159290A publication Critical patent/JPS6159290A/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

  • Heat-Exchange Devices With Radiators And Conduit Assemblies (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】 〔発明の技術分野〕 本発明は高速増殖炉に係り、特に原子炉容器の取付構造
の改良に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to fast breeder reactors, and more particularly to improvements in the mounting structure of nuclear reactor vessels.

〔発明の技術的背景〕[Technical background of the invention]

一般に液体ナトリウム等の液体金属を冷却材とする液体
金属冷却型高速増殖炉では、原子炉容器は軽水炉に比べ
て高速中性子を2けた程度馬く受けるので、中性子損傷
の少ない5tJS304などのオーステナイト系ステン
レス鋼が材料としてよく用いられている。この原子炉容
器の内部には炉心が収容されかつ冷゛却材が一定液位で
貯溜されており、しかも冷却材液面は冷却材と空気との
接触を断つために不活性ガスで覆われている。したがっ
て、原子炉容器は内部を密閉構造とする必要があり、従
来では原子炉容器の上部開口を遮蔽する上部遮蔽体の下
面に原子炉容器の上端を溶接結合して密閉構造を保つよ
うに構成されている。
In general, in liquid metal-cooled fast breeder reactors that use liquid metal such as liquid sodium as a coolant, the reactor vessel receives about two orders of magnitude more fast neutrons than in light water reactors, so the reactor vessel is made of austenitic stainless steel such as 5t JS304, which has less neutron damage. Steel is often used as a material. Inside this reactor vessel, a reactor core is housed and coolant is stored at a constant level, and the coolant liquid level is covered with inert gas to prevent contact between the coolant and air. ing. Therefore, the inside of the reactor vessel must have a sealed structure. Conventionally, the upper end of the reactor vessel was welded to the lower surface of the upper shield that shields the upper opening of the reactor vessel to maintain a sealed structure. has been done.

ところが、上部遮蔽体は原子炉容器に比べて熱衝撃が少
ないので通常炭素鋼が材料として用いられており、その
ために原子炉容器と上部遮蔽体との溶接箇所は異材溶接
となり、しかもこの溶接部分には原子炉容器の温度変化
による熱応力が加わる。このため従来においては原子炉
容器と上部遮蔽体との溶接部に割れなどの溶接欠陥が発
生し、原子炉の健全性を損うおそれがあり、また狭隈な
場所での溶接作業となるため作業能率が悪く、溶接作業
に長時間を要すという不具合もあった。そこでこのよう
な問題を解消するために、本発明者らは先に次のような
原子炉容器の取付構造を提案している。
However, since the upper shield is subject to less thermal shock than the reactor vessel, carbon steel is usually used as a material.For this reason, the welding points between the reactor vessel and the upper shield are dissimilar metal welds, and this welded portion is subjected to thermal stress due to temperature changes in the reactor vessel. For this reason, in the past, welding defects such as cracks occurred in the weld between the reactor vessel and the upper shield, which could impair the integrity of the reactor, and the welding work had to be done in a confined space. Another problem was that work efficiency was poor and welding work took a long time. In order to solve this problem, the present inventors have previously proposed the following attachment structure for a nuclear reactor vessel.

第2図および第3図はその提案例を示す図で、第2図は
タンク型高速増殖炉の概略構成を示し、第3図は第2図
の■部を拡大して示したものである。図中1はステンレ
ン鋼からなる原子炉容器であって、この原子炉容器1の
開口縁部には径方向に突出したフランジ2が形成されて
いる。原子炉容器1の周囲は据付基礎3で囲まれており
、この据付基礎3の上部には原子炉容器1を支持するリ
ングガータ4が載置されている。このリングガータ4の
内周面上部には溝部5が形成され、この溝部5に前記フ
ランジ2を係合させて原子炉容器1を支持するように構
成されている。また、原子炉容器1の上部開口には鋼板
を組立てた円盤形をなす上部遮蔽体としてのルーフスラ
ブ6が設置され、原子炉容器1を遮蔽している。このル
ーフスラブ6には中間熱交換器7および循環ポンプ8等
が複数台搭載されており、原子炉容器1内に挿入されて
いる。
Figures 2 and 3 are diagrams showing examples of the proposal, with Figure 2 showing the schematic configuration of a tank-type fast breeder reactor, and Figure 3 showing an enlarged view of the ■ part in Figure 2. . In the figure, reference numeral 1 denotes a reactor vessel made of stainless steel, and a radially projecting flange 2 is formed at the opening edge of the reactor vessel 1. As shown in FIG. The reactor vessel 1 is surrounded by an installation foundation 3, and a ring gutter 4 that supports the reactor vessel 1 is placed on top of the installation foundation 3. A groove 5 is formed in the upper part of the inner peripheral surface of the ring gutter 4, and the flange 2 is engaged with the groove 5 to support the reactor vessel 1. Further, a roof slab 6 as an upper shielding body in the form of a disc made of assembled steel plates is installed at the upper opening of the reactor vessel 1 to shield the reactor vessel 1 . This roof slab 6 is equipped with a plurality of intermediate heat exchangers 7, circulation pumps 8, etc., and is inserted into the reactor vessel 1.

原子炉容器1内には多数の燃料集合体(図示せず)から
なる炉心9が収容され、さ′らに冷却材としての液体ナ
トリウム10が一定液位を保つように貯溜されている。
A reactor core 9 consisting of a large number of fuel assemblies (not shown) is accommodated within the reactor vessel 1, and liquid sodium 10 as a coolant is stored so as to maintain a constant liquid level.

また、冷却材液面とルーフスラブ6下面との間の空間部
にはカバーガスとしてのアルゴンガス11が充填されて
いる。上記ルーフスラブ6の中央部には円形の開口部が
形成され、この開口部には回転プラグ12が嵌め込まれ
ている。この回転プラグ12には炉心上部機構13およ
び制御棒駆動機構14等が搭載され、制御棒駆動機構1
4は制御棒(図示せず)を炉心9に対して上方より挿入
または引抜いて炉心9の核反応を制御するように構成さ
れている。
Further, the space between the coolant liquid level and the lower surface of the roof slab 6 is filled with argon gas 11 as a cover gas. A circular opening is formed in the center of the roof slab 6, and a rotary plug 12 is fitted into this opening. This rotary plug 12 is equipped with a core upper mechanism 13, a control rod drive mechanism 14, etc., and the control rod drive mechanism 1
Reference numeral 4 is configured to control the nuclear reaction in the reactor core 9 by inserting or withdrawing a control rod (not shown) from above into the reactor core 9 .

また、原子炉容器1の周囲には安全容器15が設けられ
、万一原子炉容器1に漏洩が生じたとしたも液体ナトリ
ウム10が流出しないように構成されている。そして、
原子炉容器1は運転状態によって常温から500℃程度
まで温度が変化し、この温度変化に伴って熱変形を繰り
返すため、前記フランジ2は第3図に示す如くリングガ
ータ4との間に径方向に所定の間隙16を形成して係合
されている。また、フランジ2とリングガータ4との間
には周方向の移動を禁止するラジアルキー17が設けら
れ、フランジ2およびリングガータ4の上面には上下方
向の移動を禁止する押圧板18が固定されている。従っ
て、原子炉容器1は径方向にのみ移動自在となってリン
グガータ4で支持されている。また、前記ルーフスラブ
6の外周にはスカート19が一体となって設けられてい
る。このスカート19はルーフスラブ6の外周に下方が
開口した環状の内部空間20を形成して取付けられてお
り、その下端はフランジ2の上面に突設された環状の薄
肉突起21に衝合して溶接結合され、原子炉容器1とル
ーフスラブ6との気密を保持するように構成されている
Further, a safety container 15 is provided around the reactor vessel 1 to prevent liquid sodium 10 from flowing out even if a leak occurs in the reactor vessel 1. and,
The temperature of the reactor vessel 1 changes from room temperature to about 500°C depending on the operating condition, and thermal deformation occurs repeatedly due to this temperature change. Therefore, the flange 2 is radially spaced between the ring gutter 4 and the ring gutter 4 as shown in FIG. are engaged with each other with a predetermined gap 16 formed therebetween. Further, a radial key 17 is provided between the flange 2 and the ring gutter 4 to prevent movement in the circumferential direction, and a pressing plate 18 is fixed to the upper surface of the flange 2 and the ring gutter 4 to prevent movement in the vertical direction. ing. Therefore, the reactor vessel 1 is supported by the ring gutter 4 and is movable only in the radial direction. Further, a skirt 19 is integrally provided on the outer periphery of the roof slab 6. This skirt 19 is attached to the outer periphery of the roof slab 6 to form an annular internal space 20 that is open at the bottom, and its lower end abuts against an annular thin-walled projection 21 projecting from the upper surface of the flange 2. The reactor vessel 1 and the roof slab 6 are welded together and configured to maintain airtightness between the reactor vessel 1 and the roof slab 6.

このように先の提案例では原子炉容器1およびルーフス
ラブ6はスカート19と薄肉突起21とで溶接結合され
ているため、原子炉容器1の径方向の熱変形をスカート
19と薄肉突起21の変形で吸収することができるので
、スカート19と薄肉突起21との溶接部に原子炉容器
1の熱変形による過大な熱応力が加わることはなく、溶
接部の信頼性を向上させることができる。また、スカー
ト19と薄肉突起21との溶接作業はルーフスラブ6の
外周にて行うことができるので、狭限な場所で溶接を行
う必要がなく、溶接作業を容易かつ短時間で行うことも
できるなどの利点がある。
In this way, in the previously proposed example, the reactor vessel 1 and the roof slab 6 are welded together by the skirt 19 and the thin-walled protrusion 21. Since the stress can be absorbed by deformation, excessive thermal stress due to thermal deformation of the reactor vessel 1 is not applied to the weld between the skirt 19 and the thin protrusion 21, and the reliability of the weld can be improved. Further, since the welding work between the skirt 19 and the thin-walled protrusion 21 can be performed on the outer periphery of the roof slab 6, there is no need to perform welding in a narrow space, and the welding work can be performed easily and in a short time. There are advantages such as

〔背景技術の問題点〕[Problems with background technology]

このように先の提案例では種々の利点を有しているが、
実際にこれを使用する場合法のような改良の余地があっ
た。すなわちスカート19と薄肉突起21とを溶接する
際、その開先合せ、芯出し。
In this way, the previous proposed example has various advantages, but
When actually using this method, there is room for improvement. That is, when welding the skirt 19 and the thin protrusion 21, groove alignment and centering.

レベル調整等の作業が容易かつ正確に行える必要がある
。また、溶接後の開先内面検査や原子炉運転開始後の供
用期間中検査に対応できるようにしなければならない。
It is necessary to perform work such as level adjustment easily and accurately. In addition, it must be possible to handle inner surface inspections of grooves after welding and inspections during the service period after the start of reactor operation.

〔発明の目的〕[Purpose of the invention]

本発明はこのような事情にもとづいてなされたもので、
その目的とするところは原子炉容器の密閉構造として有
効で、容易かつ短時間で現地溶接が行えると共に溶接後
の開先内面検査を実施でき、異材溶接継手部の信頼性お
よ゛び健全性を向上させた高速増殖炉を提供することに
ある。
The present invention was made based on these circumstances, and
Its purpose is to be effective as a hermetic structure for nuclear reactor vessels, to enable easy and quick on-site welding, to inspect the inner surface of grooves after welding, and to improve the reliability and soundness of dissimilar metal weld joints. The objective is to provide a fast breeder reactor with improved performance.

(発明の概要) 本発明は上記の目的を達成するために、前記スカートの
外周面にラグを突出して設けるとともに、前記スカート
と上部遮蔽体外周との間の内部空間に溶接部を検査する
台車が走行するレールを設けたものである。
(Summary of the Invention) In order to achieve the above-mentioned object, the present invention provides a protruding lug on the outer peripheral surface of the skirt, and a trolley for inspecting welded parts in the internal space between the skirt and the outer periphery of the upper shield. It is equipped with rails on which the trains run.

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

以下、本発明の実施例を図面を参照して説明する。 Embodiments of the present invention will be described below with reference to the drawings.

第1図は本発明の一実施例を示す図で、図中第3図と同
一部分には同一符号が付しである。本実施例では前記の
提案例に加えてスカート19の外周面上部には環状に張
出したラグ22が設けられている。また、スカート19
とル−フスフプロ外周との間に形成された環状の内部空
間20にはスカート19と薄肉突起21との溶接部を検
査する台車(図示せず)が走行するためのレール23が
設けられており、ルーフスラブ6の外周面に固定されて
いる。さらにルーフスラブ6の上面縁部には貫通孔24
が穿設され、上記内部空間20に通じている。なお、こ
の貫通孔24は通常プラグ25によって閉塞されている
FIG. 1 is a diagram showing an embodiment of the present invention, in which the same parts as in FIG. 3 are given the same reference numerals. In this embodiment, in addition to the above-mentioned proposed example, an annularly projecting lug 22 is provided on the upper part of the outer peripheral surface of the skirt 19. Also, skirt 19
An annular internal space 20 formed between the outer periphery of the skirt 19 and the roof protrusion 21 is provided with a rail 23 on which a trolley (not shown) for inspecting the welded portion between the skirt 19 and the thin protrusion 21 runs. , is fixed to the outer peripheral surface of the roof slab 6. Furthermore, a through hole 24 is provided at the upper edge of the roof slab 6.
is bored and communicates with the internal space 20. Note that this through hole 24 is normally closed with a plug 25.

次にこのような構成によるスカート1つと薄肉突起21
との溶接手順を説明するが、ここでは原子炉容器1がス
テンレス鋼製で、ルーフスラブ6が炭素muの場合につ
いて説明する。まずスカート19の下端にステンレス鋼
をバタリング(肉盛溶接)した後、図示せぬクレーンで
スカート19を含むルーフスラブ全体を原子炉容器1の
上部近傍まで吊下ろす。次にこの状態でフランジ2とラ
グ22との間に油圧ジヤツキ(図示せず)を設置し、ク
レーンを下げながら油圧ジヤツキの高さを調節してスカ
ート1つと薄肉突起21との開先位置合せを行う。そし
て、両者の開先が正しい゛位置に設定されたことを確認
した後、スカート19と薄肉突起21とのステンレス鋼
どうしの溶接を行う。
Next, one skirt and thin protrusion 21 with such a configuration
The welding procedure will be described below, but here we will explain the case where the reactor vessel 1 is made of stainless steel and the roof slab 6 is made of carbon mu. First, after battering (overlay welding) stainless steel to the lower end of the skirt 19, the entire roof slab including the skirt 19 is lowered to near the top of the reactor vessel 1 using a crane (not shown). Next, in this state, install a hydraulic jack (not shown) between the flange 2 and the lug 22, and adjust the height of the hydraulic jack while lowering the crane to align the groove between one skirt and the thin protrusion 21. I do. After confirming that both grooves are set at the correct position, the skirt 19 and the thin protrusion 21 are welded together using stainless steel.

このように本実施例によればスカート19の外周面にラ
グ22を設けたことにより、スカート19と薄肉突起2
1との溶接部の開先合せ、芯出し、レベル調整等を油圧
ジヤツキ等を用いて容易かつ正確に行うことができる。
In this way, according to this embodiment, by providing the lugs 22 on the outer peripheral surface of the skirt 19, the skirt 19 and the thin protrusion 2
Groove alignment, centering, level adjustment, etc. of the welded part with 1 can be easily and accurately performed using a hydraulic jack or the like.

またルーフスラブ外周の内部空間20にレール23を設
けたことにより、各種の非破壊検査装置を内部空間20
側から溶接部に接近させることができるため目視検査等
の溶接部の内面検査が可能となり、原子炉運転開始後の
供用期間中検査にも対応できる。さらにレール23は内
部空間20の下部を狭めているので、上記空間へのナト
リウム蒸気や核分裂生成物(FP)を含む、ガスの侵入
量低減にも寄与できる。
Furthermore, by providing the rail 23 in the internal space 20 around the outer periphery of the roof slab, various non-destructive inspection devices can be installed in the internal space 20.
Since the welded part can be approached from the side, it is possible to inspect the internal surface of the welded part, such as visual inspection, and it can also be used for inspections during the service period after the start of reactor operation. Furthermore, since the rail 23 narrows the lower part of the internal space 20, it can also contribute to reducing the amount of gases, including sodium vapor and fission products (FP), entering the space.

なお、本・発明は上記実施例に限定されるものではない
。たとえば上記実施例では原子炉容器1がステンレス鋼
製で、ルーフスラブ6が炭素鋼製の場合について説明し
たが、本発明によれば材料の組合わせに関係なく適用で
きる。また、上記実施例ではタンク型高速増殖炉に適用
した例を示したが、例えばループ型等その他各種形式の
高速増殖炉にも適用できるのは勿論である。
Note that the present invention is not limited to the above embodiments. For example, in the above embodiment, a case has been described in which the reactor vessel 1 is made of stainless steel and the roof slab 6 is made of carbon steel, but the present invention can be applied regardless of the combination of materials. Further, in the above embodiment, an example was shown in which the present invention was applied to a tank type fast breeder reactor, but it is of course applicable to other types of fast breeder reactors such as a loop type, for example.

〔発明の効果〕〔Effect of the invention〕

以上説明したように本発明によれば、上方が開口しその
同口縁部に径方向に突出したフランジを有しかつ内部に
炉心を収容する原子炉容器と、この原子炉容器の上部間
口を遮蔽する上部遮蔽体と、前記原子炉容器の周囲に形
成された据付基礎と、この据付基礎の上部に載置され前
記原子炉容器のフランジを下方より支持するリングガー
タと、前記上部遮蔽体の外周に一体に設けられ上部遮蔽
体外周との間に下方が開口した環状の内部空間を形成す
るスカートと、前記原子炉容器のフランジ上面に突設さ
れ前記スカートの下端に衝合して溶接結合される薄肉突
起と、前記スカートの外周面に突出して取付けられるラ
グと、前記内部空間内に設けられ前記薄肉突起とスカー
トとの溶接部を検査する台車が走行するレールとを具備
したので、原子炉容器の密閉構造として有効で、容易か
つ短時間で現地溶接が行えると共に溶接後の開先内面検
査を実施でき、異材溶接継手部の信頼性および健全性を
向上させた高速増殖炉を提供できる。
As explained above, according to the present invention, there is provided a reactor vessel which is open at the top and has a radially protruding flange on the edge of the mouth and houses a reactor core therein, and an upper opening of the reactor vessel. An upper shielding body for shielding, an installation foundation formed around the reactor vessel, a ring gutter placed on the upper part of the installation foundation and supporting the flange of the reactor vessel from below, and a ring gutter for supporting the flange of the reactor vessel from below; a skirt that is integrally provided on the outer periphery and forms an annular internal space that is open at the bottom between it and the outer periphery of the upper shield; and a skirt that protrudes from the upper surface of the flange of the reactor vessel and abuts against the lower end of the skirt and is welded to the outer periphery of the upper shield. A thin-walled protrusion, a lug protruding from and attached to the outer peripheral surface of the skirt, and a rail provided in the internal space on which a trolley runs to inspect the welded portion between the thin-walled protrusion and the skirt. It is effective as a sealed structure for the reactor vessel, allows easy and quick on-site welding, and enables inspection of the inner surface of the groove after welding, providing a fast breeder reactor with improved reliability and soundness of dissimilar metal weld joints. .

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

第1図は本発明の一実施例を示すタンク型高速増殖炉の
原子炉容器とルーフスラブの一部を拡大した断面図、第
2図および第3図は本発明者らによって先に提案された
原子炉容器の取付構造を示す図で、第2図はタンク型高
速増殖炉の概略構成を示す縦断面図、第3図は第2図の
頂部を拡大した断面図である。 1・・・原子炉容器、2・・・フランジ、3・・・据付
基礎、4・・・リングガータ、6・・・ルーフスラブ、
9・・・炉心、19・・・スカート、21・・・薄肉突
起、22・・・ラグ、23・・・レール。
FIG. 1 is an enlarged cross-sectional view of a part of the reactor vessel and roof slab of a tank-type fast breeder reactor showing one embodiment of the present invention, and FIGS. FIG. 2 is a longitudinal sectional view showing the schematic structure of a tank-type fast breeder reactor, and FIG. 3 is an enlarged sectional view of the top of FIG. 2. 1... Reactor vessel, 2... Flange, 3... Installation foundation, 4... Ring gutter, 6... Roof slab,
9... Core, 19... Skirt, 21... Thin protrusion, 22... Lug, 23... Rail.

Claims (3)

【特許請求の範囲】[Claims] (1)上方が開口しその開口縁部に径方向に突出したフ
ランジを有しかつ内部に炉心を収容する原子炉容器と、
この原子炉容器の上部開口を遮蔽する上部遮蔽体と、前
記原子炉容器の周囲に形成された据付基礎と、この据付
基礎の上部に載置され前記原子炉容器のフランジを下方
より支持するリングガータと、前記上部遮蔽体の外周に
一体に設けられ上部遮蔽体外周との間に下方が開口した
環状の内部空間を形成するスカートと、前記原子炉容器
のフランジ上面に突設され前記スカートの下端に衝合し
て溶接結合される薄肉突起と、前記スカートの外周面に
突出して取付けられるラグと、前記内部空間内に設けら
れ前記薄肉突起とスカートとの溶接部を検査する台車が
走行するレールとを具備したことを特徴とする高速増殖
炉。
(1) A reactor vessel that is open at the top, has a radially protruding flange on the edge of the opening, and houses a reactor core therein;
An upper shield that shields the upper opening of the reactor vessel, an installation foundation formed around the reactor vessel, and a ring that is placed on top of the installation foundation and supports the flange of the reactor vessel from below. a gutter, a skirt that is integrally provided on the outer periphery of the upper shield and forms an annular internal space with an opening at the bottom between the outer periphery of the upper shield; and a skirt that is provided protrudingly on the upper surface of the flange of the reactor vessel and that A thin-walled protrusion that abuts and is welded to the lower end, a lug that is protrudingly attached to the outer peripheral surface of the skirt, and a trolley that is provided in the interior space and that inspects the welded portion between the thin-walled protrusion and the skirt runs. A fast breeder reactor characterized by comprising a rail.
(2)前記スカートは前記薄肉突起と同種材料をバタリ
ングした後に溶接結合されることを特徴とする特許請求
の範囲1項記載の高速増殖炉。
(2) The fast breeder reactor according to claim 1, wherein the skirt is welded together after buttering the same material as the thin-walled protrusion.
(3)前記原子炉容器および薄肉突起はステンレス鋼よ
りなることを特徴とする特許請求の範囲第1項記載の高
速増殖炉。
(3) The fast breeder reactor according to claim 1, wherein the reactor vessel and the thin protrusion are made of stainless steel.
JP59181837A 1984-08-31 1984-08-31 Fast breeder reactor Pending JPS6159290A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59181837A JPS6159290A (en) 1984-08-31 1984-08-31 Fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59181837A JPS6159290A (en) 1984-08-31 1984-08-31 Fast breeder reactor

Publications (1)

Publication Number Publication Date
JPS6159290A true JPS6159290A (en) 1986-03-26

Family

ID=16107675

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59181837A Pending JPS6159290A (en) 1984-08-31 1984-08-31 Fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS6159290A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2925974A1 (en) * 2007-12-28 2009-07-03 Areva Np Sas CLOSURE SLAB OF A MAIN TANK OF A NUCLEAR REACTOR WITH QUICK NEUTRONS

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2925974A1 (en) * 2007-12-28 2009-07-03 Areva Np Sas CLOSURE SLAB OF A MAIN TANK OF A NUCLEAR REACTOR WITH QUICK NEUTRONS
WO2009083676A3 (en) * 2007-12-28 2009-08-27 Areva Np Cover slab for the main nuclear reactor vessel of a fast breeder reactor

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