JPS6312277B2 - - Google Patents
Info
- Publication number
- JPS6312277B2 JPS6312277B2 JP55072801A JP7280180A JPS6312277B2 JP S6312277 B2 JPS6312277 B2 JP S6312277B2 JP 55072801 A JP55072801 A JP 55072801A JP 7280180 A JP7280180 A JP 7280180A JP S6312277 B2 JPS6312277 B2 JP S6312277B2
- Authority
- JP
- Japan
- Prior art keywords
- plug
- rotating
- reactor
- fixed
- rotary
- 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
Links
- 238000002844 melting Methods 0.000 description 10
- 230000008018 melting Effects 0.000 description 10
- 229910045601 alloy Inorganic materials 0.000 description 7
- 239000000956 alloy Substances 0.000 description 7
- 229910052751 metal Inorganic materials 0.000 description 7
- 239000002184 metal Substances 0.000 description 7
- 239000000446 fuel Substances 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 238000005192 partition Methods 0.000 description 3
- 238000007789 sealing Methods 0.000 description 3
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 102100027340 Slit homolog 2 protein Human genes 0.000 description 1
- 101710133576 Slit homolog 2 protein Proteins 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 229920001971 elastomer Polymers 0.000 description 1
- 239000000806 elastomer Substances 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は例えば液体金属を冷却材とする高速増
殖炉のしやへいプラグに係り、特に回転プラグの
原子炉運転中の固定方法を改良した原子炉しやへ
いプラグに関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to, for example, a shielding plug for a fast breeder reactor that uses liquid metal as a coolant, and particularly relates to a nuclear reactor shielding plug that improves the method of fixing a rotating plug during reactor operation. .
高速炉用のしやへいプラグは原子炉容器の上部
にあり放射線と熱しやへい機能を保持しつつ、燃
料交換のため気密を保ちながら、1重、2重又は
3重に回転する構造のものが広く採用されてい
る。しやへいプラグのうち、前述した回転するプ
ラグを回転プラグと呼び静止部を固定プラグと呼
ぶ。この回転プラグは燃料交換時に必要な気密を
保つたまま必要な精度で旋回させ、かつ原子炉運
転中は静止状態で必要な気密を保持させるため
に、通常次の様な方式を採用している。 The shield plug for fast reactors is located at the top of the reactor vessel and has a structure that rotates in single, double, or triple rotations while maintaining radiation and heat shielding functions and maintaining airtightness for fuel exchange. has been widely adopted. Among the flexible plugs, the above-mentioned rotating plug is called a rotating plug, and the stationary part is called a fixed plug. This rotating plug usually uses the following method in order to rotate with the necessary precision while maintaining the necessary airtightness during fuel exchange, and to maintain the necessary airtightness in a stationary state during reactor operation. .
(イ) 回転部シールとして抵融点金属シールを用
い、回転プラグ旋回時にはこの金属シールを溶
融状態とし、原子炉運転中は凝固状態とする。(a) A low melting point metal seal is used as the rotating part seal, and this metal seal is in a molten state when the rotating plug rotates, and is in a solidified state during reactor operation.
(ロ) 必要に応じて前記金属シールのバツクアツプ
としてエラストマシールを併用する。(b) If necessary, use an elastomer seal as a backup for the metal seal.
(ハ) 旋回精度向上のため、ボールベアリングを使
用する。ボールベアリングの負荷条件を緩和す
るために、回転プラグ旋回させる時には油圧持
上装置等により回転プラグを持上げて回転プラ
グの全荷重をボールベアリングに作用させる。(c) Use ball bearings to improve turning accuracy. In order to alleviate the load conditions on the ball bearing, when the rotary plug is turned, the rotary plug is lifted by a hydraulic lifting device or the like so that the entire load of the rotary plug is applied to the ball bearing.
(ニ) 原子炉運転中は回転プラグは、ボールベアリ
ングを介さず直接固定プラグ上に安置され、転
倒防止策を講じる。(d) During reactor operation, the rotating plug is placed directly on the fixed plug without using ball bearings, and measures are taken to prevent it from tipping over.
以上の方式を採用する場合、原子炉運転中に地
震が発生した場合に次の点で改善の余地があり、
改善策が望まれていた。 When adopting the above method, there is room for improvement in the following points if an earthquake occurs during reactor operation.
Improvement measures were desired.
(1) 上記(ニ)により回転プラグ全体の転倒は防止で
きるが、回転プラグは固定プラグとのギヤツプ
分だけ水平移動する可能性がある。制御棒を確
実にスクラムさせるためにはこの水平移動分も
含めて設計しておく必要があり、制御棒スクラ
ム機能確保のための設計をより一層工夫の必要
なものとしている。(1) Although the above (d) prevents the entire rotating plug from falling over, there is a possibility that the rotating plug may move horizontally by the gap between it and the fixed plug. In order to reliably scram the control rods, it is necessary to include this horizontal movement in the design, making the design to ensure the control rod scram function even more ingenious.
(2) 原子炉運転中は、回転プラグシールの低融点
金属を凝固状態としているため、(1)項の如く回
転プラグが水平移動すると、この低融点金属シ
ール部に強制変位を与える。この強制部材とこ
のシール金属との接触状態に変化をきたすため
地震時のシール性能が変化するおそれがある。(2) During reactor operation, the low melting point metal of the rotating plug seal is in a solidified state, so when the rotating plug moves horizontally as described in item (1), this low melting point metal seal section is forcibly displaced. Since the contact state between the forcing member and the seal metal changes, there is a risk that the sealing performance during an earthquake will change.
本発明は上記の事情に鑑みてなされたもので、
地震等の振動が発生しても安定して回転プラグを
保持し得る原子炉しやへいプラグを提供すること
を目的とする。 The present invention was made in view of the above circumstances, and
An object of the present invention is to provide a nuclear reactor shielding plug that can stably hold a rotating plug even when vibrations such as earthquakes occur.
以下、図面を参照しながら本発明の一実施例に
ついて説明する。 An embodiment of the present invention will be described below with reference to the drawings.
第1図は本発明に係る原子炉しやへいプラグの
縦断面図である。この図において原子炉容器1は
原子炉の支持構造物20に上端部を支えられて保
持されている。この原子炉容器1の蓋となつてい
る原子炉しやへいプラグの概略構成は原子炉容器
1の上縁部に固定された固定プラグ2と、この固
定プラグ2と嵌合して貫通載置される回転プラグ
3とからなつている。この回転プラグ3を貫通し
て炉心上部機構4が設けられており、またこの回
転プラグ3は主要強度部材となつている回転プラ
グ上板31と、この回転プラグ上板31の下方に
ある回転プラグ下板と、回転プラグ上板31の上
側縁に固着された回転プラグライザ32とから構
成されている。 FIG. 1 is a longitudinal sectional view of a nuclear reactor shielding plug according to the present invention. In this figure, a reactor vessel 1 is supported and held at its upper end by a support structure 20 of the reactor. The reactor shield plug, which serves as the lid of the reactor vessel 1, has a schematic structure including a fixed plug 2 fixed to the upper edge of the reactor vessel 1, and a fixed plug 2 that is fitted into the fixed plug 2 and inserted through the reactor. It consists of a rotating plug 3. A core upper mechanism 4 is provided passing through this rotating plug 3, and this rotating plug 3 includes a rotating plug upper plate 31 which is a main strength member, and a rotating plug located below this rotating plug upper plate 31. It consists of a lower plate and a rotary plug riser 32 fixed to the upper edge of a rotary plug upper plate 31.
この回転プラグライザ32の上には大歯車7が
取り付けられており、前記固定プラグ2上に設け
られた回転駆動機構10に取り付けられた小歯車
9を介して前記大歯車7を回転できるようになつ
ている。また大歯車7の上には油圧持上げ装置8
が取り付けられており前記回転プラグライザ32
を介して回転プラグを引上げられるように構成さ
れている。固定プラグ2には円筒状の支持部材2
1があり、ボールベアリング6を介して大歯車7
を支持できるようになつており、また支持部材2
1の内側には低融点合金シール5を受容し得る円
環槽22が設けられている。そして前記回転プラ
グライザ32の外側に設けられた円筒仕切板23
が前記円環槽22中に貯溜された低融点合金シー
ル5中に浸漬されることによつて回転プラグ3と
固定プラグ2との気密が保たれる。 A large gear 7 is mounted on the rotary plug riser 32, and the large gear 7 can be rotated via a small gear 9 attached to a rotational drive mechanism 10 provided on the fixed plug 2. It's summery. Also, on top of the large gear 7 is a hydraulic lifting device 8.
is attached to the rotary plug riser 32.
The rotary plug is configured to be pulled up via the rotary plug. The fixed plug 2 has a cylindrical support member 2.
1, and a large gear 7 via a ball bearing 6
It is designed to be able to support the supporting member 2.
1 is provided with an annular tank 22 capable of receiving a low melting point alloy seal 5. A cylindrical partition plate 23 provided on the outside of the rotary plug riser 32
The rotating plug 3 and the stationary plug 2 are kept airtight by being immersed in the low melting point alloy seal 5 stored in the annular tank 22.
第1図中記号Aで示し、これを第2図に拡大し
て示すように、回転プラグ3を構成している回転
プラグ上板31の下部周縁には円環状にガイドブ
レード33が突設されている。またこのガイドブ
レード33と当接する部位の固定プラグ2の上面
には円溝状の凹部であるガイドスリツト21が設
けられている。 As shown by symbol A in FIG. 1 and enlarged in FIG. 2, a guide blade 33 is provided in an annular shape protruding from the lower peripheral edge of the rotary plug upper plate 31 constituting the rotary plug 3. ing. Further, a guide slit 21, which is a circular groove-shaped recess, is provided on the upper surface of the fixed plug 2 at a portion that comes into contact with the guide blade 33.
上記のように構成された本発明に係る原子炉し
やへいプラグの動作について説明する。 The operation of the nuclear reactor shield plug according to the present invention configured as described above will be explained.
原子炉停止時において大歯車7の上に設けられ
た油圧持上装置8を作動させて回転プラグ3を持
ち上げると回転プラグ上板31の下部に突設され
たガイドブレード33と固定プラグ上面に設けら
れたガイドスリツト21とが離れる。従つて回転
プラグ3の回転モーメントに対する抵抗力は、こ
の部位では発生しない。そしてボールベアリング
6に支持された回転プラグらは、回転駆動機構1
0の駆動によつて大歯車7および小歯車9を介し
て回転されることになる。そしてこの回転プラグ
3に取り付けられている炉心上部機構4を原子炉
容器内の所定の部位に位置せしめて、原子炉容器
1内に設置されている図示しない原子炉炉心の燃
料棒の交換等の作業を行なう。 When the hydraulic lifting device 8 provided on the large gear 7 is activated to lift the rotary plug 3 during reactor shutdown, a guide blade 33 protruding from the lower part of the rotary plug upper plate 31 and a guide blade 33 provided on the upper surface of the fixed plug are activated. The guide slit 21 is separated. Therefore, no resistance force against the rotational moment of the rotating plug 3 is generated at this location. The rotary plugs supported by the ball bearing 6 are rotated by the rotary drive mechanism 1.
0, it is rotated via the large gear 7 and the small gear 9. Then, the core upper mechanism 4 attached to the rotary plug 3 is positioned at a predetermined position in the reactor vessel, and the reactor core upper mechanism 4, which is attached to the rotary plug 3, is positioned at a predetermined position within the reactor vessel 1 to perform operations such as replacing fuel rods in the reactor core (not shown) installed in the reactor vessel 1. do the work.
一方原子炉の起動に際しては、油圧持上装置8
を作動させて回転プラグ3を降下させる。すると
前記ガイドブレード33は前記ガイドスリツト2
1中に挿入されて嵌合し、回転プラグ3は固定プ
ラグ2に載置されて支持されることとなる。つま
り、ガイドブレード33とガイドスリツト21が
嵌合されている結果、地震等の振動が発生しても
固定プラグ2と回転プラグ3との相対位置がずれ
ることが無い。 On the other hand, when starting up the reactor, the hydraulic lifting device 8
is activated to lower the rotating plug 3. Then, the guide blade 33 moves into the guide slit 2.
The rotary plug 3 is inserted into the fixed plug 2 and fitted, and the rotary plug 3 is placed on and supported by the fixed plug 2. That is, as a result of the guide blade 33 and the guide slit 21 being fitted together, the relative positions of the fixed plug 2 and the rotating plug 3 will not shift even if vibrations such as an earthquake occur.
なお、説明した実施例においては回転プラグに
凸状のガイドブレードを設け、固定プラグに凹状
のガイドスリツトを設けた構成としたが、逆に固
定プラグに凸状のガイドブレードを設け、回転プ
ラグに凹状のガイドスリツトを設けた構成として
も良い。またガイドブレードは必ずしも円環状で
なくても良く、凸状のブロツクを円周上に配置し
た構成としても良い。 In the described embodiment, the rotating plug is provided with a convex guide blade and the fixed plug is provided with a concave guide slit, but conversely, the fixed plug is provided with a convex guide blade and the rotating plug is provided with a concave guide slit. It is also possible to have a configuration in which a guide slit is provided. Further, the guide blade does not necessarily have to be annular, and may have a configuration in which convex blocks are arranged on the circumference.
以上説明したように本発明に係る原子炉しやへ
いプラグは、原子炉運転中に地震が生じた場合で
も、固定プラグ2に対する回転プラグ上板31の
相対移動を防止できる結果、制御棒スクラム機能
維持能力を向上させることができる。また低融点
合金シール部に強制変位を与えないため円筒仕切
板等に大きな応力が発生せず十分な構造強度を維
持でき、円筒仕切板等と低融点合金シール5との
接触状態も変化しないため安定したシール機能を
維持できる。 As explained above, the reactor shielding plug according to the present invention can prevent the relative movement of the rotating plug upper plate 31 with respect to the fixed plug 2 even if an earthquake occurs during reactor operation, and as a result, the control rod scram function is achieved. Maintenance ability can be improved. In addition, since no forced displacement is applied to the low melting point alloy seal portion, sufficient structural strength can be maintained without generating large stress on the cylindrical partition plate, etc., and the contact state between the cylindrical partition plate etc. and the low melting point alloy seal 5 does not change. Can maintain stable sealing function.
さらに、ガイドブレード33とガイドスリツト
21部がかん合しているため、この部分がガス流
れの抵抗部となる結果原子炉カバーガス圧力が急
激な変動をしても、その圧力変動が回転プラグシ
ールの低融点合金シール5に直接伝わらず緩和さ
れて伝わるため、回転プラグのシール性能がさら
に安定したものとなる。 Furthermore, since the guide blade 33 and the guide slit 21 part are engaged, this part acts as a gas flow resistance part, and even if the reactor cover gas pressure fluctuates rapidly, the pressure fluctuation will be suppressed by the rotating plug seal. Since it is not directly transmitted to the low melting point alloy seal 5 but is transmitted in a relaxed manner, the sealing performance of the rotating plug becomes even more stable.
又原子炉容器内に貯溜されたナトリウムから発
生するナトリウム蒸気が低融点合金シール5部分
に移行するのをほゞ完全に防止できるため、この
合金シールの性能劣化をおさえることができる。 Furthermore, it is possible to almost completely prevent the sodium vapor generated from the sodium stored in the reactor vessel from migrating to the low melting point alloy seal 5 portion, thereby suppressing the performance deterioration of this alloy seal.
第1図は本発明に係る原子炉しやへいプラグの
縦断面図、第2図は第1図におけるガイドブレー
ド部(A部)を拡大して示す縦断面図である。
1……原子炉容器、2……固定プラグ、3……
回転プラグ、31……回転プラグ上板、5……低
融点金属シール、21……ガイドスリツト、33
……ガイドブレード。
FIG. 1 is a vertical cross-sectional view of a nuclear reactor shielding plug according to the present invention, and FIG. 2 is a vertical cross-sectional view showing an enlarged guide blade portion (section A) in FIG. 1. 1...Reactor vessel, 2...Fixing plug, 3...
Rotating plug, 31... Rotating plug upper plate, 5... Low melting point metal seal, 21... Guide slit, 33
...Guide blade.
Claims (1)
グと、この固定プラグに貫挿された回転プラグと
からなるしやへいプラグにおいて、前記回転プラ
グの下面に円周上に設けられた凸部を形成し、前
記固定プラグに前記凸部と嵌合する円溝状の凹部
を形成してなることを特徴とする原子炉しやへい
プラグ。 2 回転プラグの下面に円溝状の凹部を形成し、
固定プラグの上面に前記凹部と嵌合する凸部を形
成してなることを特徴とする特許請求の範囲第1
項記載の原子炉しやへいプラグ。[Scope of Claims] 1. In a flexible plug that closes an upper opening of a reactor vessel and is composed of a fixed plug and a rotating plug inserted through the fixed plug, a circumferential portion is provided on the lower surface of the rotating plug. What is claimed is: 1. A nuclear reactor shielding plug, characterized in that the fixing plug is formed with a convex portion, and a circular groove-shaped concave portion that fits into the convex portion is formed in the fixed plug. 2 Forming a circular groove-shaped recess on the lower surface of the rotating plug,
Claim 1, characterized in that a convex portion that fits into the concave portion is formed on the upper surface of the fixing plug.
Nuclear reactor shield plug as described in section.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7280180A JPS57590A (en) | 1980-06-02 | 1980-06-02 | Shielding plug of nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7280180A JPS57590A (en) | 1980-06-02 | 1980-06-02 | Shielding plug of nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57590A JPS57590A (en) | 1982-01-05 |
| JPS6312277B2 true JPS6312277B2 (en) | 1988-03-18 |
Family
ID=13499849
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP7280180A Granted JPS57590A (en) | 1980-06-02 | 1980-06-02 | Shielding plug of nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57590A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4552083A (en) * | 1983-11-28 | 1985-11-12 | Lockheed Missiles & Space Co., Inc. | High-speed semisubmerged ship maneuvering system |
-
1980
- 1980-06-02 JP JP7280180A patent/JPS57590A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57590A (en) | 1982-01-05 |
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