JPS6089794A - Nuclear reactor - Google Patents
Nuclear reactorInfo
- Publication number
- JPS6089794A JPS6089794A JP58197508A JP19750883A JPS6089794A JP S6089794 A JPS6089794 A JP S6089794A JP 58197508 A JP58197508 A JP 58197508A JP 19750883 A JP19750883 A JP 19750883A JP S6089794 A JPS6089794 A JP S6089794A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- core
- lid member
- reactor vessel
- nuclear reactor
- 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.)
- Granted
Links
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
- Treatment Of Water By Oxidation Or Reduction (AREA)
- Analysing Materials By The Use Of Radiation (AREA)
- Monitoring And Testing Of Nuclear Reactors (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】 本発明は原子炉の改良に関するものである。[Detailed description of the invention] The present invention relates to improvements in nuclear reactors.
従来の高速増殖炉を第１図により説明すると−（１）が
原子炉容器、（２）が炉心、（３）が上記原子炉容器（
１）の冷却材入口ノズル、（４）が上記原子炉容器（１
）の冷却材出口ノズル−（５）が上記原子炉容器（１）
の上端開口部に装着した遮蔽プラグ、（６）が炉心上部
機構、（７）が制御棒駆動装置−（８）が原子炉の出力
を制御する制御棒、（９）が回転プラグ−（１０１が燃
料交換機で、冷却拐（一般には金属ナトリウム）が冷却
材入口ノズル（３）から原子炉容器（１１内に入り一炉
心（２）により熱せられて、冷却材出口ノズル（４）か
ら流出する。A conventional fast breeder reactor is explained using Fig. 1. (1) is the reactor vessel, (2) is the reactor core, and (3) is the reactor vessel (
1) is the coolant inlet nozzle, (4) is the coolant inlet nozzle of the reactor vessel (1).
) The coolant outlet nozzle (5) of the reactor vessel (1)
The shielding plug attached to the upper end opening, (6) is the core upper mechanism, (7) is the control rod drive device - (8) is the control rod that controls the reactor output, (9) is the rotating plug - (101 is a fuel exchanger, in which coolant (generally sodium metal) enters the reactor vessel (11) through the coolant inlet nozzle (3), is heated by the reactor core (2), and flows out through the coolant outlet nozzle (4). .
この冷却材である金属ナトリウムは、化学的活性が強い
ため、冷却材バウンダリにシール機構を設けないのが一
般的である。上記原子炉は、有液面方式で、液面上方の
空間部が不活性ガス（一般にはアルゴンガス）の雰囲気
下にある。遮蔽プラグ（５）及び回転プラグ（９）は不
活性ガスの隔離壁の役目↑
をもち、原子炉容器（１）の蓋になって（・る。原子炉
の出力制御は、炉心（２）を構成する燃料集合体の間に
置いた制御棒（８）を上下させることにより行なわれ一
制御棒（８）の上下動は、遮蔽プラグ（５）を貫通して
設けられた炉心上部機構（６）内の制御棒駆動装置（７
）を作動して５行なわれるようにｔ「つて〜・る。Since metallic sodium, which is the coolant, has strong chemical activity, it is common to not provide a sealing mechanism at the coolant boundary. The above-mentioned nuclear reactor is of a liquid level type, and the space above the liquid level is under an atmosphere of inert gas (generally argon gas). The shielding plug (5) and the rotating plug (9) serve as an inert gas isolation wall, and act as a lid for the reactor vessel (1).The power control of the reactor is controlled by the reactor core (2). The vertical movement of the control rods (8) is performed by moving the control rods (8) up and down, which are placed between the fuel assemblies that make up the core. control rod drive device (7) in
) to perform 5 steps.
前記原子炉では、燃料交換の際に、燃料集合体を吊上げ
て、入れ替える必要があるか−こｆ）燃料交換を遮蔽プ
ラグ（５）を貫通して設置した燃料交換機ＱＯ）により
行なっている。このためには−制御棒駆動装置（７）を
含む炉心上部機構（６）を炉心（２）の上部から退去さ
せなくてはならず−これを可能にするために、炉心上部
機構（６）、を炉心（２）の中心に対しｉＡ心した回転
プラグ（９）に設置し、燃料交換時九、Ｉ司回転プラグ
（９）を回転して、炉心上部機構（６）を炉心（２）の
直上から退去するようにしており、燃料交換機Ｏｒ＋＋
も炉心（２）の燃料集合体の全てにとどかせる必２Ｍま
たは３重の回転構造体とし、そのどれかに′ＣＣ炉上上
部機構６）が貫通している回転プラグ以外のプラグに）
燃料交換機００）を貫通、設陥している。In the above-mentioned nuclear reactor, when changing fuel, it is necessary to lift the fuel assembly and replace it.f) Fuel exchange is performed using a fuel exchanger QO installed through the shielding plug (5). To do this - the upper core assembly (6) including the control rod drives (7) must be moved out of the upper part of the core (2) - to make this possible, the upper core assembly (6) , is installed in the rotating plug (9) that is aligned with the center of the reactor core (2), and during refueling, the I-center rotating plug (9) is rotated and the upper core mechanism (6) is aligned with the center of the reactor core (2). The fuel exchange machine Or++
It must be a 2M or 3-fold rotating structure that can be delivered to all fuel assemblies in the reactor core (2), and any plug other than the rotating plug through which the CC reactor upper mechanism 6) passes through.
The fuel exchanger 00) has been penetrated and damaged.
し示しこのような構造では、回転プラグ（９）の径がか
なり大きくなり、これが原子炉容器（１）の径を大きく
する要因になっている。However, in such a structure, the diameter of the rotating plug (9) becomes considerably large, which is a factor in increasing the diameter of the reactor vessel (1).
本発明は前記の問題点に対処するもので、制御棒駆動装
置を有する炉心上部機構と、原子炉容器の上端開口部を
閉じる蓋部材とを具え、前記炉心上部機構を前記蓋部材
を貫通して同蓋部材に昇降可能に装着したことを特徴と
する原子炉に係り一その目的とする処は、回転プラグの
径ひいては原子炉容器の径を小さくできて、製作コスト
を低減できる改良された原子炉を供する点にある。The present invention addresses the above-mentioned problems and includes an upper core mechanism having a control rod drive device and a lid member that closes an opening at the upper end of a reactor vessel, and the upper core mechanism is inserted through the lid member. The purpose of this nuclear reactor is to reduce the manufacturing cost by reducing the diameter of the rotating plug and the diameter of the reactor vessel. The point is that it provides nuclear reactors.
次に本発明の原子炉を第２，３図に示す一実施例により
説明すると−（］）が原子炉容器−（２）が炉心へ（３
）（４）が冷却材である全町ナトリウムの入口ノズル及
び出口ノズル、（５）が原子炉容器（１）の蓋部材であ
り一本実施例では−この蓋（的が１重のまた炉心（２）
と同心の回転プラグになっている。また（６）が前記蓋
部材（回転プラグ）（５つを貫通して設けられた炉心上
部機構で、その内部に制御棒駆動装置（７）及びその他
の機器類を収納している。（９′）が案内棒、（ｌのが
同案内棒（９’）Ｖｃ摺動自在に嵌挿されるとともに炉
心上部機構（６）の上端部に取付けられたフランジ−（
１１）が原子炉容器（１）内のカバーガスを外気に対し
て隔離するシールベロー （１２１が前記案内枠（９つ
の上部を固定保持するための固定環、（１３１が遮蔽筒
である。なお固定環α２は、その周囲が床または構造物
（１１３１に対して回転可能に支持されている。Next, the nuclear reactor of the present invention will be explained with reference to an embodiment shown in Figs. 2 and 3.
) (4) are the inlet and outlet nozzles of Zenmachi sodium, which is the coolant, and (5) is the lid member of the reactor vessel (1). (2)
It is a concentric rotating plug. In addition, (6) is the core upper mechanism installed through the lid member (rotary plug) (5), and the control rod drive device (7) and other equipment are housed inside it. (9 ') is a guide rod, (l is the same guide rod (9'), and Vc is slidably inserted into the flange (9') attached to the upper end of the core upper mechanism (6).
11) is a seal bellow that isolates the cover gas in the reactor vessel (1) from outside air. The fixed ring α2 is rotatably supported around the floor or structure (1131).
０椙ま炉心上部機構（６）の案内車である。This is the guide wheel for the upper core mechanism (6).
次に前記原子炉の作用を説明する。原子炉の通常運転時
には、炉心（２）内に挿入された制御棒を上下させる制
御棒駆動装置（７）を含む炉心上部機構（６）は、炉心
（２）の直上に第２図に示すように置かれている。燃料
を交換するときには、制御棒と制御棒駆動機構（７）と
を切離して、炉心上部機構（６）を上方へ引上げる。こ
の状態を第３図 に示した。この引上げる際の横ゆれ防
止及びガイドのために案内棒（９’）を設けている。フ
ランジ（１０’）はこの案内棒（９つに沿って昇降する
。案内の補助として案内車０舶を設けるのが有効である
。なお案内棒（９′）も案内車（１４）も本実施例に限
定されない。本発明では炉心上部機構（６）を上記のよ
うに昇降させるので、炉内カバーガスのシールのために
イローズαυを設けている。炉心上部機構（６）を昇降
させるための昇降駆動装置としては一前記案内棒（９′
）をネジ棒とじ−これをフランジ（１０つに螺合し、案
内棒（ｇ″）を回転させて、炉心上部機構（６）を昇降
させるもの、或いはフランジ（１的の上に設けたアイボ
ルトにローブを掛は一上方からクレーンにより引上げる
もの等を使用する。上述のよ５に炉心上部機構（６）を
上方へ引上げると、炉心（２）の直上には、燃料を交換
する上で邪魔なものがなくなり、その後は、燃料交換機
（１５）を用い、蓋（回転プラグ）（５）を回転して、
燃料交換作業を行なう。なお０３）は−シールベローα
υの内側にあがってくる放射性カバーガスに対する放射
線遮蔽壁である。Next, the operation of the nuclear reactor will be explained. During normal operation of the reactor, the upper core mechanism (6) including the control rod drive device (7) that moves the control rods inserted into the reactor core (2) up and down is located directly above the reactor core (2) as shown in Figure 2. It is placed like this. When exchanging fuel, the control rods and control rod drive mechanism (7) are separated and the core upper mechanism (6) is pulled upward. This state is shown in Figure 3. A guide rod (9') is provided to prevent lateral shaking and guide during this pulling up. The flange (10') moves up and down along these guide rods (9). It is effective to provide a guide wheel (0) to assist guidance. Note that both the guide rod (9') and the guide wheel (14) are The present invention is not limited to this example. In the present invention, since the core upper mechanism (6) is raised and lowered as described above, an eraser αυ is provided for sealing the cover gas in the reactor. The lifting drive device includes one guide rod (9').
) are screwed together with a threaded rod - these are screwed together into flanges (threaded together, and the guide rod (g'') is rotated to raise and lower the core upper mechanism (6), or the flanges (eye bolts installed on top of the The upper part of the reactor core (2) is lifted up using a crane from above. Once there are no obstacles in the way, use the fuel exchanger (15) and rotate the lid (rotary plug) (5).
Carry out fuel exchange work. Note that 03) is - seal bellow α
It is a radiation shielding wall against the radioactive cover gas rising inside υ.
本発明の原子炉は前記のように制御棒駆動装置を有する
炉心上部機構と、原子炉容器の上端開口部を閉じる蓋部
材とを具え、前記炉心上部機構を前記蓋部材を貫通して
同蓋部材に昇降可能に装着しており、燃料又換時に炉心
上部機構を炉心の直上から上昇させて退去させ糺はよく
、２重または３重の蓋部材（回転プラグ）が１重の蓋部
材で済むことになり、蓋部材の小型化が可能になり−ひ
いては原子炉容器の径を縮小できて一製作コストを低減
できる効果がある。The nuclear reactor of the present invention includes an upper core mechanism having a control rod drive device as described above, and a lid member that closes the upper end opening of the reactor vessel, and the upper core mechanism is inserted through the lid member to close the upper end of the reactor vessel. It is attached to the member so that it can be raised and lowered, and when refueling, the upper core mechanism is raised and removed from directly above the core, and it is easily glued, and the double or triple lid member (rotary plug) is replaced by a single lid member. This makes it possible to reduce the size of the lid member, which in turn allows the diameter of the reactor vessel to be reduced, which has the effect of reducing manufacturing costs.
以上本発明゛を実施例について説明したが一勿論本発明
はこのような実施例にだけ局限されるものではなく、本
発明の精神を逸脱しない範囲内で種々の設計の改変を施
しうるものである。Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to such embodiments, and that various changes in design can be made without departing from the spirit of the present invention. be.
第１図は従来の原子炉を示す縦断側面図、第２図は本発
明に係る原子炉の一実施例の通常運転時の状態を示す縦
断側面図、第３図はその燃料交換時の状態を示す縦断側
面図である。
（１）・・・原子炉容器、（５）・・・蓋部材、（６）
・・・炉心上部機構、（７）・・・制御棒駆動装置。
復代理人 弁理士開本重文
（外３名）
第１図
第２図FIG. 1 is a vertical side view showing a conventional nuclear reactor, FIG. 2 is a vertical side view showing the state of an embodiment of the nuclear reactor according to the present invention during normal operation, and FIG. 3 is the state at the time of fuel replacement. FIG. (1) Reactor vessel, (5) Lid member, (6)
... Core upper mechanism, (7) ... Control rod drive device. Sub-agent: Patent Attorney Kaimoto Important Information (3 others) Figure 1 Figure 2
Claims (1)
上端開口部を閉じる蓋部材とを具え、前記炉心上部機構
を前記蓋部材を貫通して同蓋部材に昇降可能に装着した
ことを特徴とする原子炉。It is characterized by comprising an upper core mechanism having a control rod drive device and a lid member that closes an upper end opening of the reactor vessel, and the upper core mechanism is attached to the lid member so as to be able to rise and lower through the lid member. nuclear reactor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58197508A JPS6089794A (en) | 1983-10-24 | 1983-10-24 | Nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58197508A JPS6089794A (en) | 1983-10-24 | 1983-10-24 | Nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6089794A true JPS6089794A (en) | 1985-05-20 |
| JPH0422230B2 JPH0422230B2 (en) | 1992-04-16 |
Family
ID=16375636
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58197508A Granted JPS6089794A (en) | 1983-10-24 | 1983-10-24 | Nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6089794A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6367594A (en) * | 1986-09-09 | 1988-03-26 | 財団法人 電力中央研究所 | Fast breeder reactor |
-
1983
- 1983-10-24 JP JP58197508A patent/JPS6089794A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6367594A (en) * | 1986-09-09 | 1988-03-26 | 財団法人 電力中央研究所 | Fast breeder reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0422230B2 (en) | 1992-04-16 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US3533911A (en) | Nuclear reactor systems | |
| JPS6089794A (en) | Nuclear reactor | |
| JPS63111496A (en) | Fuel processor for fast neutron type reactor | |
| JPS61181992A (en) | Nuclear reactor | |
| JPS60162995A (en) | Nuclear reactor | |
| JP2856864B2 (en) | Fast breeder reactor | |
| JPH0552979A (en) | Small-sized fast breeder reactor | |
| EP0240602A2 (en) | Fuel transfer means | |
| JPH0160799B2 (en) | ||
| JPH0321516Y2 (en) | ||
| JP3340398B2 (en) | How to handle the reactor pressure vessel | |
| JPS635297A (en) | Upper structure of fast breeder reactor | |
| JPS6122798B2 (en) | ||
| JPH11231082A (en) | Fast neutron reactor | |
| JPS63214690A (en) | Nuclear reactor | |
| JPS63217300A (en) | Fuel taking-in-out device | |
| JPH11190795A (en) | Fuel exchanging machine of fast reactor | |
| JPS61155794A (en) | Shielding open-close structure of through-port | |
| JPH04215098A (en) | Control rod device for fast breeder | |
| JPS6385397A (en) | Stop device for nuclear reactor | |
| JPS5934399U (en) | Upper guide tube handling machine for reactor control rod drive mechanism | |
| JPH10148698A (en) | Fast reactor | |
| JPS6151755B2 (en) | ||
| JPS5853797A (en) | Guide tube for refueling in sodium cooled reactor | |
| JPS6275297A (en) | Fast breeder reactor |