JPS6151755B2 - - Google Patents
Info
- Publication number
- JPS6151755B2 JPS6151755B2 JP55064994A JP6499480A JPS6151755B2 JP S6151755 B2 JPS6151755 B2 JP S6151755B2 JP 55064994 A JP55064994 A JP 55064994A JP 6499480 A JP6499480 A JP 6499480A JP S6151755 B2 JPS6151755 B2 JP S6151755B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- fuel
- casing
- passage
- furnace
- 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
- 239000000446 fuel Substances 0.000 claims description 41
- 239000000463 material Substances 0.000 claims description 7
- 230000003028 elevating effect Effects 0.000 claims description 2
- 230000005855 radiation Effects 0.000 description 8
- 239000012857 radioactive material Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 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】
この発明は液体金属冷却高速増殖炉における燃
料交換に際して、原子炉炉内の燃料交換機と炉外
側を走行する燃料出入機との間で炉内外にまたが
つて燃料を受け渡しする炉内中継装置、特にその
炉外しやへい体の構造に関するものである。Detailed Description of the Invention This invention provides a system for transferring fuel between the inside and outside of the reactor between a fuel exchange machine inside the reactor and a fuel inlet/output machine running outside the reactor during fuel exchange in a liquid metal cooled fast breeder reactor. The present invention relates to an in-furnace relay device, particularly the structure of the furnace outlet and shield body.
まず第１図により燃料交換系統の概要を述べ
る。図において、１は原子炉容器、２は上部しや
へいプラグ、３はその回転プラグ、４は炉心であ
り、回転プラグ３には燃料交換機５、およびしや
へいプラグ２には本発明の対象である炉内中継装
置６がそれぞれ搭載設置されている。炉心４を構
成している燃料は燃料交換機５および炉内中継装
置６を経由して、燃料出入機７との間で受け渡し
され、使用済燃料の搬出および新燃料の装荷が行
われる。なお符号８は回転プラグ３に搭載したプ
ラグ回転駆動、燃料交換機の運転制御、その他炉
心制御など各種の炉上機器を示している。 First, an overview of the fuel exchange system will be described with reference to Figure 1. In the figure, 1 is the reactor vessel, 2 is the upper shingle plug, 3 is its rotating plug, and 4 is the reactor core. An in-furnace relay device 6 is installed in each case. The fuel constituting the reactor core 4 is transferred to and from a fuel inlet/output machine 7 via a fuel exchanger 5 and an in-core relay device 6, and spent fuel is carried out and new fuel is loaded. Note that the reference numeral 8 indicates various on-core equipment such as a plug rotation drive mounted on the rotary plug 3, operation control of a fuel exchanger, and other core control.
一方、炉内中継装置６の従来における一般構造
を示すと第２図および第３図のごとくである。す
なわち装置６は大きく分けるとしやへいプラグ２
を貫通して炉内に挿入される本体機構６１と炉外
側しやへい体６２から成る。本体機構６１は上下
方向に延在する燃料案内管６１１と、案内管６１
１の先端に位置する回転ラツク６１２と、案内管
６１１の側方に添つて上下に延在する回転ラツク
駆動軸６１３と、案内管６１１および駆動軸６１
３を包囲した格納管６１４から成る。これに対し
炉外側しやへい体６２はしやへいプラグ２の上に
載置した放射線しやへい材の筒形ケーシング６２
１と、ケーシング６２１の頂部に結合したドアバ
ルブ６２２より成り、かつケーシング６２１の下
端の段部６２３に係止して前記本体機構６１を吊
下げ支持している。なお６３は回転ラツクの駆動
装置を示す。上記の構成で燃料交換時にはドアバ
ルブ６２２を開いて炉外に待機している本体機構
６１を炉内へ挿入セツトし、更にドアバルブに燃
料出入機７を接続した状態で回転ラツク６１２を
中継して炉内側の燃料交換機と炉外側の燃料出入
機７との間で燃料９の受け渡しを行う。特に中継
装置６における燃料９の昇降移送は、燃料出入機
７のグリツパで燃料９を掴み、案内管６１１およ
びケーシング６２１内の通路６２４を通じて行わ
れる。燃料交換が終了すれば、本体機構６１は炉
内より引上げ、ドアバルブ６２２を通じて外方へ
引出される。 On the other hand, the conventional general structure of the in-furnace relay device 6 is shown in FIGS. 2 and 3. In other words, the device 6 can be broadly divided into the plug 2
It consists of a main body mechanism 61 that is inserted into the furnace by penetrating through it, and a furnace outer shield body 62. The main body mechanism 61 includes a fuel guide pipe 611 extending in the vertical direction;
1, a rotating rack drive shaft 613 extending vertically along the side of the guide tube 611, and a rotating rack 612 located at the tip of the guide tube 611 and the drive shaft 61.
It consists of a storage pipe 614 that surrounds 3. On the other hand, the shielding body 62 outside the furnace is a cylindrical casing 62 made of radiation-resistant material placed on the shielding plug 2.
1 and a door valve 622 connected to the top of the casing 621, and is engaged with a step 623 at the lower end of the casing 621 to suspend and support the main body mechanism 61. Note that 63 indicates a drive device for the rotating rack. With the above configuration, when replacing fuel, the door valve 622 is opened, the main body mechanism 61 waiting outside the furnace is inserted and set, and the fuel inlet/output device 7 is connected to the door valve, and the rotary rack 612 is relayed to the furnace. Fuel 9 is transferred between the fuel exchange machine on the inside and the fuel inlet/output machine 7 on the outside of the furnace. In particular, the fuel 9 is moved up and down in the relay device 6 by gripping the fuel 9 with the gripper of the fuel inlet/outlet device 7 and passing through the guide pipe 611 and the passage 624 in the casing 621 . When the fuel exchange is completed, the main body mechanism 61 is lifted out of the furnace and pulled out through the door valve 622.
上記のように炉外側しやへい体６２は、炉内と
燃料出入機７との間にまたがつてカバーガス雰囲
気に維持した燃料移送用の通路６２４を形成する
ものであり、したがつて放射線防護の管理面から
も炉外側しやへい体６２が安全基準を満たすだけ
の十分な放射線しやへい性能を備えていることが
要求される。このしやへい性能はケーシング６２
１を構成している鉛などのしやへい材の厚さ寸法
により決まる。ところでケーシング６２１にあけ
た通路６２４の径寸法は本体機構６１の引上げ通
過に十分な内径寸法に設定されているのに対し、
本体機構６１の案内管６１１は駆動軸６１３と並
んで格納管６１４内に収容されているので偏心位
置している。このために、第３図のように燃料９
の昇降経路となる案内管６１１を中心に同心的に
外形を定めてケーシング６２１を円筒形状に構成
したとすると、左側領域では十分なしやへい厚さ
l1が設定できるが、必然的に駆動軸側の右側領域
ではしやへい厚さがl2のように小となり、放射線
しやへい性能の低下を招く。かかる点から格納管
６１４を中心として全周域で所要のしやへい厚さ
l1を定めて円筒形のケーシング６２１を構成しよ
うとするとその外形寸法は鎖線のようになり、実
線の外径D1に対しD2のごとくケーシング６２１
が大形化する。しかも一方では第１図で述べたよ
うに原子炉のしやへいプラグ上には限られたスペ
ース内に数多くの各種炉上機器８を据付けられね
ばならないことから、一般には各種機器の配置条
件を最優先にして据付けのレイアウトが決定され
る。このために自ずと炉外側しやへい体６２も占
有スペースが制限され、他の機器との干渉を避け
るためにもできる限り外形寸法が小形であること
が要求される。この結果、多くの場合にはケーシ
ング６２１の外形寸法を第３図の鎖線のように大
形にするだけの占有スペースが炉上に確保できな
いことから、実際には実線形状にするか、ないし
は小形炉で第１図のレイアウトのようにケーシン
グと他の炉上機器８とが接近する場合には、第３
図における点線から右方の部分をカツトするよう
にケーシングの一部を切欠いてまで外形寸法の小
形化が強制される。したがつてこのままではしや
へい厚さの不足をきたし、ケーシング外へ漏れる
照射線量率が安全基準を満たさなくなる恐れが生
じる。 As mentioned above, the outer-furnace shield body 62 forms a fuel transfer passage 624 maintained in a cover gas atmosphere between the inside of the furnace and the fuel inlet/outlet device 7, and therefore prevents radiation. From the standpoint of protection management, it is required that the reactor outer shield body 62 has sufficient radiation shielding performance to meet safety standards. This strong performance is achieved by Casing 62.
It is determined by the thickness of the flexible material such as lead that composes 1. By the way, while the diameter of the passage 624 formed in the casing 621 is set to an inner diameter sufficient for the main body mechanism 61 to be pulled up and passed through,
The guide tube 611 of the main body mechanism 61 is housed in the storage tube 614 along with the drive shaft 613, so that it is eccentrically positioned. For this purpose, as shown in Figure 3, the fuel 9
If the casing 621 is configured in a cylindrical shape with the outer shape concentrically defined around the guide pipe 611 which is the elevating path for the
Although it is possible to set l 1 , the shielding thickness inevitably becomes small as l 2 in the right region on the drive shaft side, resulting in a decrease in radiation shielding performance. From this point, the required insulation thickness is determined in the entire circumference around the storage pipe 614.
If l 1 is determined and a cylindrical casing 621 is constructed, its external dimensions will be as shown by the chain line .
becomes larger. On the other hand, as mentioned in Fig. 1, a large number of various types of reactor equipment 8 must be installed within a limited space on the reactor's shield plug, so generally speaking, the arrangement conditions for various equipment must be adjusted. The installation layout is determined with top priority. For this reason, the space occupied by the furnace outer shield body 62 is naturally limited, and the outer dimensions are required to be as small as possible in order to avoid interference with other equipment. As a result, in many cases, it is not possible to secure enough space on the furnace to increase the outer dimensions of the casing 621 as shown by the chain line in Figure 3, so in reality, it is necessary to make the casing 621 a solid line shape or to make it smaller. When the casing and other furnace equipment 8 are close to each other in the furnace as in the layout shown in Fig. 1, the third
The external dimensions are forced to be reduced by cutting out part of the casing to the right of the dotted line in the figure. Therefore, if this continues, the thickness will be insufficient, and there is a risk that the radiation dose rate leaking out of the casing will no longer meet safety standards.
本発明は上記の点にかんがみなされたものであ
り、その目的は前記した従来のケーシングにおけ
るしやへい厚さ不足を巧みに解消して十分な放射
線しやへい性能を確保しつつ、外形寸法の小形化
が図れるようにした炉内中継装置の炉外側しやへ
い体を提供することにある。 The present invention has been made in consideration of the above points, and its purpose is to skillfully solve the problem of the lack of thickness in the conventional casing, ensure sufficient radiation resistance performance, and reduce the external dimensions. An object of the present invention is to provide an outer-furnace shield for an in-furnace relay device that can be downsized.
以下本発明を図示実施例に基づいて詳述する。 The present invention will be described in detail below based on illustrated embodiments.
第４図および第５図において、ケーシング６２
１の通路内に本発明に基づく補助しやへい体６４
が挿入されている。該補助しやへい体６４は放射
線しやへい材より作られており、かつ本体機構６
１の外径および案内管６１１の内径寸法に合わせ
て外径寸法d1および内径寸法d2を定めた筒体とし
て成る。しかも内径d2の燃料通路６４１は、本体
機構６１の案内管６１１と連なるように補助しや
へい体６４の偏心した位置にあけられている。ま
た補助しやへい体６４は頂部にハンドリング用の
グラブ係合溝６４２を備えている。かかる補助し
やへい体６４は燃料交換に際して本体機構６１を
挿入セツトした後に、ドアバルブ６２２を通じて
ケーシング６２１の通路６２４へ吊降され、燃料
通路６４１を案内管６１１の位置に合わせて図示
のように本体機構６１の上に載置される。したが
つてケーシング６２１の径大な通路６２４は燃料
通過に必要な通路を残して残余空間が補助しやへ
い体６４のしやへい材で満たされ、燃料出入機７
のグリツパ７１で掴まれた燃料９は図示のごとく
補助しやへい体６４の燃料通路６４１を通じて昇
降移送されることになる。燃料交換終了後は、前
記と逆の手順でまず補助しやへい体６４を引出し
た後に本体機構６１が炉外に取出される。 In FIGS. 4 and 5, the casing 62
1, an auxiliary shield body 64 according to the invention is provided in the passageway of
is inserted. The auxiliary shield body 64 is made of radiation-resistant material, and the main body mechanism 6
The guide tube 611 is formed as a cylindrical body with an outer diameter dimension d 1 and an inner diameter dimension d 2 determined in accordance with the outer diameter of the guide tube 611 and the inner diameter dimension of the guide tube 611 . Moreover, the fuel passage 641 having an inner diameter d 2 is opened at an eccentric position of the auxiliary shield body 64 so as to be continuous with the guide pipe 611 of the main body mechanism 61 . Further, the auxiliary shield body 64 is provided with a grab engagement groove 642 for handling at the top. After the main body mechanism 61 is inserted and set during fuel exchange, the auxiliary shield body 64 is suspended into the passage 624 of the casing 621 through the door valve 622, and the fuel passage 641 is aligned with the guide pipe 611, and the main body mechanism 61 is inserted and set as shown in the figure. It is placed on the mechanism 61. Therefore, the large-diameter passage 624 of the casing 621 leaves a passage necessary for fuel passage, and the remaining space is filled with the flexible material of the auxiliary shield body 64, and the fuel inlet/outlet device 7
The fuel 9 gripped by the gripper 71 is moved up and down through the fuel passage 641 of the auxiliary shield body 64 as shown. After the fuel exchange is completed, the auxiliary shield body 64 is first pulled out and then the main body mechanism 61 is taken out of the furnace in the reverse order to the above.
さて上記の構成によれば、第３図で述べたケー
シング６２１のしやへい厚さ不足は、第５図のよ
うに補助しやへい体６４によつて補われ、燃料通
路６４１を中心とするケーシング６２１の全周域
で照射線量率の安全基準を十分満足するように実
効的なしやへい厚さがl3になる。しかもケーシン
グ６２１の外径寸法は第３図の実線径D1と同様
である。 Now, according to the above configuration, the insufficient thickness of the casing 621 described in FIG. 3 is compensated for by the auxiliary shield body 64 as shown in FIG. The effective shrinkage thickness is l 3 so as to fully satisfy the safety standards for the irradiation dose rate over the entire circumference of the casing 621. Furthermore, the outer diameter of the casing 621 is the same as the solid line diameter D1 in FIG.
上述のように本発明は炉内中継装置の本体機構
が通過できるのに十分な内径寸法の通路を形成し
たしやへい材のケーシングに対し、該ケーシング
の通路内に燃料昇降通路を残して残余空間をしや
へい材で満たすように内、外径寸法を定めた補助
しやへい体を取出し可能に挿入設置したものであ
る。したがつて従来の炉外側しやへい体における
しやへい厚さ不足は補助しやへい体により解消さ
れ、ケーシングの外形寸法を大形化することなし
に十分な放射しやへい性能を得ることができる。
このことは特に狭い炉上スペース内に数多くの各
種炉上機器と並べて炉内中継装置を据付ける場合
に極めて有利である。 As described above, the present invention provides a casing made of a sinter material that has a passage with an inner diameter sufficient for the main body mechanism of an in-core relay device to pass through, and a fuel lifting passage left in the passage of the casing. An auxiliary shield body with inner and outer diameters is removably inserted so as to fill the space with a flexible material. Therefore, the lack of thickness of the shield in the conventional furnace outer shield body can be solved by the auxiliary shield body, and sufficient radiation shielding performance can be obtained without increasing the external dimensions of the casing. I can do it.
This is particularly advantageous when the in-furnace relay device is installed alongside a large number of various on-furnace equipment in a narrow above-furnace space.
なお本発明はいままで説明した炉内中継装置の
ほかに、炉外の放射性物質貯蔵設備における放射
性物質の搬入、搬出装置などにも応用可能であ
る。 In addition to the in-core relay device described above, the present invention can also be applied to equipment for carrying in and out of radioactive materials in radioactive material storage facilities outside the reactor.
第１図は原子炉の燃料交換系統を示す構成配置
図、第２図は従来における炉内中継装置の一般構
造を示す縦断面図、第３図は第２図における矢視
−の拡大断面図、第４図は本発明一実施例の
構造を示す縦断面図、第５図は第４図における矢
視−断面図である。
１……原子炉容器、２……しやへいプラグ、６
……炉内中継装置、７……燃料出入機、９……燃
料、６１……本体機構、６１１……燃料案内管、
６２……炉外側しやへい体、６２１……ケーシン
グ、６２２……ドアバルブ、６２３……本体機構
の係止段部、６２４……ケーシングの通路、６４
……補助しやへい体、６４１……燃料通路。
Figure 1 is a configuration diagram showing the fuel exchange system of a nuclear reactor, Figure 2 is a vertical sectional view showing the general structure of a conventional in-reactor relay device, and Figure 3 is an enlarged sectional view taken in the direction of the arrow in Figure 2. , FIG. 4 is a longitudinal cross-sectional view showing the structure of one embodiment of the present invention, and FIG. 5 is a cross-sectional view taken in the direction of the arrows in FIG. 4. 1... Reactor vessel, 2... Shiyahei plug, 6
...Furnace relay device, 7...Fuel inlet/output machine, 9...Fuel, 61...Main body mechanism, 611...Fuel guide pipe,
62... Furnace outside shield body, 621... Casing, 622... Door valve, 623... Locking step of main body mechanism, 624... Passage in casing, 64
...Auxiliary body, 641...Fuel passage.
Claims (1)
に挿入した炉内中継装置の本体機構を炉外へ引き
出し可能に吊り下げ支持し、かつ頂部に結合する
燃料出入機としやへいプラグとの間で炉内外にま
たがる燃料中継用の昇降通路を形成する原子炉炉
内中継装置の炉外側しやへい体であつて、しやへ
いプラグの上に搭載設置されかつ上下方向に炉内
中継装置の本体機構の引き上げ通過に十分な内径
寸法の通路を形成したしやへい材より成る筒形状
のケーシングと、該ケーシングの頂部に結合した
ドアバルブと、燃料が昇降できる通路空間を残し
て前記ケーシングの通路内残余空間を満たすよう
に外径寸法および燃料昇降通路の位置を定め、か
つ前記ケーシングの通路内へドアバルブを通じて
取り出し可能に挿入設置した筒形状の補助しやへ
い体とで構成したことを特徴とする原子炉炉内中
継装置の炉外側しやへい体。1 The main body mechanism of the in-core relay device inserted into the reactor through the shield plug in the upper part of the reactor is suspended and supported so that it can be pulled out of the reactor, and the fuel inlet/output machine and the shield plug are connected to the top of the reactor. This is the outer shield body of the reactor in-reactor relay device that forms a lifting passage for fuel relay between the inside and outside of the reactor. A cylindrical casing made of a flexible material in which a passage with an inner diameter sufficient for lifting and passing the main body mechanism of the device is formed, a door valve connected to the top of the casing, and the casing leaving a passage space through which fuel can ascend and descend. The outer diameter and the position of the fuel elevating passage are determined so as to fill the remaining space in the passage of the casing, and a cylindrical auxiliary shield body is inserted into the passage of the casing so that it can be taken out through the door valve. Features: A shield body outside the reactor of the reactor in-reactor relay device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6499480A JPS56162096A (en) | 1980-05-16 | 1980-05-16 | Incore reley device for shield of reactor outside |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6499480A JPS56162096A (en) | 1980-05-16 | 1980-05-16 | Incore reley device for shield of reactor outside |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56162096A JPS56162096A (en) | 1981-12-12 |
| JPS6151755B2 true JPS6151755B2 (en) | 1986-11-10 |
Family
ID=13274118
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP6499480A Granted JPS56162096A (en) | 1980-05-16 | 1980-05-16 | Incore reley device for shield of reactor outside |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS56162096A (en) |
-
1980
- 1980-05-16 JP JP6499480A patent/JPS56162096A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56162096A (en) | 1981-12-12 |
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