JPH0422230B2 - - Google Patents
Info
- Publication number
- JPH0422230B2 JPH0422230B2 JP58197508A JP19750883A JPH0422230B2 JP H0422230 B2 JPH0422230 B2 JP H0422230B2 JP 58197508 A JP58197508 A JP 58197508A JP 19750883 A JP19750883 A JP 19750883A JP H0422230 B2 JPH0422230 B2 JP H0422230B2
- Authority
- JP
- Japan
- Prior art keywords
- core
- reactor
- fuel
- lid member
- reactor vessel
- 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 - Lifetime
Links
- 239000000446 fuel Substances 0.000 description 16
- 239000002826 coolant Substances 0.000 description 9
- 239000007789 gas Substances 0.000 description 4
- 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 3
- 229910052708 sodium Inorganic materials 0.000 description 3
- 239000011734 sodium Substances 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000011261 inert gas Substances 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000003213 activating effect Effects 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 230000003028 elevating effect Effects 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000000126 substance 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
- Analysing Materials By The Use Of Radiation (AREA)
- Treatment Of Water By Oxidation Or Reduction (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
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は回転プラグ、10が燃料交換
機で、冷却材(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1内に入り、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。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の蓋になつてい
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、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、行なわれるようになつ
ている。 A conventional fast breeder reactor is explained using Figure 1.
1 is a reactor vessel, 2 is a reactor core, 3 is a coolant inlet nozzle of the reactor vessel 1, 4 is a coolant outlet nozzle of the reactor vessel 1, and 5 is attached to the upper end opening of the reactor vessel 1. A shielding plug, 6 is a core upper mechanism, 7 is a control rod drive device, 8 is a control rod that controls the output of the reactor, 9 is a rotating plug, 10 is a fuel exchanger, and the coolant (generally metallic sodium) is the coolant. The coolant enters the reactor vessel 1 through the inlet nozzle 3, is heated by the reactor core 2, and flows out through the coolant outlet nozzle 4. 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 serve as a lid for the reactor vessel 1. The power output of the reactor is controlled by moving control rods 8 placed between the fuel assemblies that make up the reactor core 2 up and down. This is done by activating the control rod drive device 7 in the upper mechanism 6.
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が、この燃料
交換を遮蔽プラグ5を貫通して設置した燃料交換
機10により行なつている。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
偏心した回転プラグ9に設置し、燃料交換時に、
同回転プラグ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10も炉心2の燃料集合体の全てにとどかせ
る必要があり、そのため、一般には、回転プラグ
9を2重または3重の回転構造体とし、そのどれ
かに(炉心上部機構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10を貫通、設置し
ている。しか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つている。 In the above-described nuclear reactor, when exchanging fuel, it is necessary to lift the fuel assembly and exchange the fuel, and this fuel exchange is performed by a fuel exchanging machine 10 installed through the shielding plug 5. To do this, the upper core mechanism 6 including the control rod drive device 7 must be removed from the upper part of the core 2. To make this possible, the upper core mechanism 6 must be moved eccentrically to the center of the core 2. When replacing fuel,
The rotary plug 9 is rotated to move the core upper mechanism 6 away from directly above the core 2, and the refueling machine 10 also needs to reach all of the fuel assemblies in the core 2. Therefore, generally, The rotating plug 9 is a double or triple rotating structure, and the fuel exchanger 10 is penetrated and installed in one of them (the plug other than the rotating plug through which the upper core mechanism 6 passes). However, in such a structure, the diameter of the rotating plug 9 becomes considerably large, and this
This is a factor that increases the diameter of the
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、
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. Relating to a nuclear reactor characterized in that it is attached to the lid member so that it can be raised and lowered,
The objective is to provide an improved nuclear reactor in which the diameter of the rotating plug and, therefore, the diameter of the reactor vessel can be reduced, thereby reducing manufacturing costs.
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、1が原子炉容器、2が炉
心、3,4が冷却材である金属ナトリウムの入口
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、本実施例では、この蓋5′が1重のま
た炉心2と同心の回転プラグになつている。また
6が前記蓋部材(回転プラグ)5′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、10′が同案内棒9′に摺動自在に嵌挿
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、12
が前記案内棒9′の上部を固定保持するための固
定環、13が遮蔽筒である。なお固定環12は、
その周囲が床または構造物16に対して回転可能
に支持されている。14は炉心上部機構6の案内
車である。 Next, the nuclear reactor of the present invention will be explained with reference to an embodiment shown in FIGS. 2 and 3. 1 is a reactor vessel, 2 is a reactor core, 3 and 4 are inlet and outlet nozzles for metallic sodium as a coolant, 5 is a lid member of the reactor vessel 1, and in this embodiment, this lid 5' is a single layered rotating plug concentric with the reactor core 2. Further, numeral 6 denotes a core upper mechanism provided through the cover member (rotary plug) 5', in which a control rod drive device 7 and other equipment are housed. 9′
is a guide rod, 10' is a flange that is slidably inserted into the guide rod 9' and is attached to the upper end of the upper core mechanism 6, and 11 is a flange that isolates the cover gas in the reactor vessel 1 from the outside air. Seal Bellow, 12
is a fixed ring for fixing and holding the upper part of the guide rod 9', and 13 is a shielding cylinder. Note that the fixed ring 12 is
Its periphery is rotatably supported relative to the floor or structure 16. 14 is a guide wheel of the core upper 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′に沿つて昇降する。案内の補助として案内車
14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ベローズ1
1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、前記案内棒9′をネ
ジ棒とし、これをフランジ10′に螺合し、案内
棒9′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10′の上に設けたアイ
ボルトにロープを掛け、上方からクレーンにより
引上げるもの等を使用する。上述のように炉心上
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
13は、シールベロー11の内側にあがつてくる
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, a core upper mechanism 6 including a control rod drive device 7 that moves control rods inserted into the reactor core 2 up and down.
is placed directly above the reactor core 2 as shown in FIG. When replacing 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 FIG. A guide rod 9' is provided to prevent sideways shaking and guide during this pulling up. The flange 10' moves up and down along this guide rod 9'. It is effective to provide a guide wheel 14 to assist in guidance. Note that neither the guide rod 9' nor the guide wheel 14 is limited to this embodiment. In the present invention, since the core upper mechanism 6 is raised and lowered as described above, the bellows 1 is used to seal the cover gas inside the reactor.
1 is provided. As an elevating drive device for raising and lowering the upper core mechanism 6, the guide rod 9' is a threaded rod, which is screwed onto the flange 10', and the guide rod 9' is rotated to raise and lower the upper core mechanism 6. Alternatively, a rope can be hung from an eye bolt provided on the flange 10', and a crane can be used to pull it up from above. When the upper core mechanism 6 is pulled upward as described above, there is nothing directly above the core 2 that will obstruct the exchange of fuel.
Thereafter, the lid (rotary plug) 5 is rotated using the fuel exchanger 15 to perform the fuel exchange operation. Note that 13 is a radiation shielding wall against the radioactive cover gas rising inside the seal bellows 11.
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、燃料交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ればよく、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、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 a member so that it can be raised and lowered, and when exchanging fuel, the upper core mechanism only needs to be raised and removed from directly above the core, and a double or triple lid member (rotary plug) can be replaced with a single lid member. Therefore, it is possible to downsize the lid member, and in turn, the diameter of the reactor vessel can 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、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 design modifications can be made without departing from the spirit of the present invention. .
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。
Figure 1 is a longitudinal side view of a conventional nuclear reactor;
FIG. 3 is a longitudinal side view showing the state of one embodiment of the nuclear reactor according to the present invention during normal operation, and FIG. 3 is a longitudinal side view showing the state during fuel exchange. DESCRIPTION OF SYMBOLS 1... Reactor vessel, 5... Lid member, 6... Core upper mechanism, 7... Control rod drive device.
Claims (1)
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。1 comprising an upper core mechanism having a control rod drive device and a lid member that closes the upper end opening of the reactor vessel,
A nuclear reactor characterized in that the core upper mechanism passes through the lid member and is attached to the lid member so as to be movable up and down.
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 JPS6089794A (en) | 1985-05-20 |
| JPH0422230B2 true 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) |
Families Citing this family (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
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6089794A (en) | 1985-05-20 |
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