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JPH06324188A - Fast breeder reactor - Google Patents

Fast breeder reactor

Info

Publication number
JPH06324188A
JPH06324188A JP5114821A JP11482193A JPH06324188A JP H06324188 A JPH06324188 A JP H06324188A JP 5114821 A JP5114821 A JP 5114821A JP 11482193 A JP11482193 A JP 11482193A JP H06324188 A JPH06324188 A JP H06324188A
Authority
JP
Japan
Prior art keywords
core
control rod
reactor core
core upper
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.)
Pending
Application number
JP5114821A
Other languages
Japanese (ja)
Inventor
Kimitaka Kimura
公隆 木村
Masaru Fukuya
賢 福家
Toru Iijima
亨 飯島
Masakazu Jinbo
雅一 神保
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 JP5114821A priority Critical patent/JPH06324188A/en
Publication of JPH06324188A publication Critical patent/JPH06324188A/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To improve inserting performance of a control rod at earthquake time by restricting relative displacement by connecting the lower end part of a reactor core upper structure to the top part of a reactor core. CONSTITUTION:A circular hole necessary for nuclear reactor operation is evaded, and a fuel aggregate 12 is arranged in the top part of a reactor core 1, and a connecting recessed part 14 is arranged in the corner square part of a hexagonal pillar 6 of a control rod lower part guiding pipe 13, and a connecting projecting part 15 is arranged in the lower end part of a reactor core upper mechanism 5, and both are fitted to each other, and the reactor core upper machanism 5 is connected to the top part of the reactor core 1. As a result, the reactor core upper mechanism 5 is not vibrated at earthquake time as a hand holding beam only by support of a fixing cover 3, and horizontal directional relative displacement is restricted, so that inserting performance of a control rod is improved remarkably. Shaft directional displacement caused by a temperature change in a nuclear reactor is absorbed when the projecting part 15 moves slidingly in the recessed part 14, and when fuel is replaced, since the projecting part 15 is pulled up together with the reactor core upper mechanism 5, work space of a gripper device can be secured.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は冷却材として液体金属ナ
トリウムを用いた高速増殖炉に関し、特に炉心上部機構
を引き上げて燃料交換を行う高速増殖炉に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fast breeder reactor using liquid metal sodium as a coolant, and more particularly to a fast breeder reactor in which the upper core mechanism is pulled up for refueling.

【0002】[0002]

【従来の技術】この種の炉心上部機構を引き上げて燃料
交換を行う液体金属ナトリウム冷却型の高速増殖炉は、
図12に示すように原子炉容器内に炉心1が収容され、
この炉心1は液体金属ナトリウムの冷却材2で覆われて
おり、原子炉容器を閉塞する固定蓋3に制御棒駆動機構
4、炉心上部機構5、および燃料交換機6が設置された
構造となっている。
2. Description of the Related Art A liquid metal sodium-cooled fast breeder reactor for pulling up an upper core mechanism of this type to exchange fuel is
As shown in FIG. 12, the reactor core 1 is housed in the reactor vessel,
This core 1 is covered with a coolant 2 of liquid metal sodium, and has a structure in which a control rod drive mechanism 4, an upper core mechanism 5 and a refueling machine 6 are installed on a fixed lid 3 that closes the reactor vessel. There is.

【0003】原子炉の出力制御および停止は、炉心上部
機構5の内部に案内される制御棒を制御棒駆動機構4に
より駆動し、炉心1に挿入することによって行われる。
また、燃料交換時には図13に示すように、まず炉心上
部機構5から制御棒駆動機構4を取り外し、そこに昇降
連結機7を取り付けた後、昇降機構8および案内筒9を
設置する。
Power control and shutdown of the nuclear reactor are carried out by driving a control rod guided inside the upper core mechanism 5 by a control rod drive mechanism 4 and inserting it into the core 1.
At the time of refueling, as shown in FIG. 13, first, the control rod drive mechanism 4 is removed from the core upper part mechanism 5, the elevating coupler 7 is attached thereto, and then the elevating mechanism 8 and the guide cylinder 9 are installed.

【0004】次いで、昇降機構8により炉心上部機構5
を上方へ引き上げる。その後、炉心上部機構5が引き上
げられた空間を使用し、燃料交換機6の下端に設けた可
変アーム10によりグリッパ装置11を炉心1の燃料棒
の上部へ導き、この燃料棒をグリッパ装置11で把持し
て交換を実施する。
Next, the elevating mechanism 8 is used to move the upper core 5
Pull up. Then, using the space in which the core upper part mechanism 5 is pulled up, the variable arm 10 provided at the lower end of the fuel exchanger 6 guides the gripper device 11 to the upper part of the fuel rod of the core 1, and the gripper device 11 grips this fuel rod. And replace it.

【0005】[0005]

【発明が解決しようとする課題】ところで、上記のよう
に構成された従来の高速増殖炉においては、燃料交換時
に燃料交換機6のグリッパ装置11を炉心1の各燃料棒
の位置まで移動させるに際し、炉心上部機構5を炉心1
の直上から引き上げなければならないため、炉心上部機
構5が固定蓋3側のみから支持される構造となってい
る。
In the conventional fast breeder reactor configured as described above, when the gripper device 11 of the fuel exchanger 6 is moved to the position of each fuel rod of the core 1 at the time of refueling, Upper core mechanism 5 to core 1
Since it has to be pulled up from directly above, the structure is such that the core upper part mechanism 5 is supported only from the fixed lid 3 side.

【0006】このため、地震時には炉心上部機構5の下
端が上部より大きく振動し、炉心1の制御棒挿入孔と炉
心上部機構5の制御棒を案内する孔とに相対位置変位が
生じることとなり、この変位が大きい場合には制御棒の
挿入性が阻害されるという問題点があった。
Therefore, at the time of an earthquake, the lower end of the core upper mechanism 5 vibrates more than the upper part, and a relative positional displacement occurs between the control rod insertion hole of the core 1 and the hole guiding the control rod of the core upper mechanism 5. When this displacement is large, there is a problem that the insertability of the control rod is hindered.

【0007】本発明は上述した事情を考慮してなされた
もので、地震時における制御棒の挿入性を向上させた高
速増殖炉を提供することを目的とする。
The present invention has been made in view of the above circumstances, and an object of the present invention is to provide a fast breeder reactor having improved control rod insertability during an earthquake.

【0008】[0008]

【課題を解決するための手段】上述した課題を解決する
ために、本発明の請求項1は、原子炉容器内に収容され
た炉心と、この炉心の制御棒挿入孔に制御棒を案内する
制御棒案内孔を設けた炉心上部機構とを有し、この炉心
上部機構を引き上げて燃料交換を行う高速増殖炉におい
て、上記炉心の頂部と上記炉心上部機構の下端部とを連
結する連結機構を設けたものである。
In order to solve the above-mentioned problems, the first aspect of the present invention relates to a core housed in a reactor vessel, and guides the control rod into a control rod insertion hole of this core. In a fast breeder reactor having a core upper part mechanism provided with control rod guide holes and pulling up the core upper part mechanism to perform fuel exchange, a connecting mechanism for connecting the top part of the core and the lower end part of the core upper part mechanism is provided. It is provided.

【0009】本発明の請求項2は、原子炉容器内に収容
された炉心と、この炉心の制御棒挿入孔に制御棒を案内
する制御棒案内孔を設けた炉心上部機構とを有し、この
炉心上部機構を引き上げて燃料交換を行う高速増殖炉に
おいて、上記炉心上部機構を囲む筒体を設け、この筒体
に上記炉心上部機構の中間部を支持する支持部材を設け
たものである。
According to a second aspect of the present invention, there is provided a core housed in a reactor vessel, and an upper core mechanism having a control rod guide hole for guiding the control rod into a control rod insertion hole of the core. In a fast breeder reactor in which the upper core mechanism is pulled up for refueling, a cylindrical body surrounding the upper core mechanism is provided, and a supporting member that supports an intermediate portion of the upper core mechanism is provided in the cylindrical body.

【0010】[0010]

【作用】上記の構成を有する本発明の請求項1において
は、炉心上部機構の下端部が炉心の頂部に連結されてい
るため、これら両者は地震時においても同一の変位が生
じ、その結果、炉心上部機構の制御棒案内孔と炉心の制
御棒挿入孔との水平方向相対変位をなくすことが可能と
なる。
In the first aspect of the present invention having the above structure, since the lower end portion of the core upper part mechanism is connected to the top portion of the core, both of them have the same displacement even at the time of earthquake, and as a result, It becomes possible to eliminate horizontal relative displacement between the control rod guide hole of the upper core mechanism and the control rod insertion hole of the core.

【0011】また、請求項2においては、炉心上部機構
の中間部が炉心上部機構を囲む筒体に設けた支持部材に
より支持されるため、地震時においても炉心上部機構の
下端部の変形が低減され、その結果、炉心の制御棒挿入
孔との水平方向相対変位が低減可能となる。
Further, according to the present invention, since the intermediate portion of the core upper part mechanism is supported by the supporting member provided in the cylindrical body surrounding the core upper part mechanism, the deformation of the lower end part of the core upper part mechanism is reduced even during an earthquake. As a result, the horizontal relative displacement of the core with respect to the control rod insertion hole can be reduced.

【0012】[0012]

【実施例】以下、本発明の実施例を図面に基づいて説明
する。
Embodiments of the present invention will be described below with reference to the drawings.

【0013】図1は本発明の第1実施例における炉心上
部機構を含む高速増殖炉の縦断面図であり、図2は図1
における実施例の主要部である炉心上部機構の下端部お
よび炉心の頂部の構造を詳細に示す斜視図である。な
お、従来の構成と同一または対応する部分には図12お
よび図13と同一の符号を用いて説明する。
FIG. 1 is a vertical sectional view of a fast breeder reactor including an upper core mechanism according to the first embodiment of the present invention, and FIG. 2 is shown in FIG.
3 is a perspective view showing in detail the structure of the lower end of the core upper part mechanism and the top of the core, which are the main parts of the embodiment in FIG. Note that the same or corresponding portions as those of the conventional configuration will be described using the same reference numerals as those in FIGS.

【0014】図1に示すように、高速増殖炉は原子炉容
器内に炉心1が収容され、この炉心1は液体金属ナトリ
ウムの冷却材2で覆われており、原子炉容器を閉塞する
固定蓋3に炉心上部機構5、および燃料交換機6が設置
されている。また、図1は燃料交換時の状態を示し、炉
心上部機構5には昇降連結機7が取り付けられるととも
に、昇降機構8および案内筒9が設けられ、昇降機構8
により炉心上部機構5の一部が上方へ引き上げられてい
る。
As shown in FIG. 1, in a fast breeder reactor, a reactor core 1 is housed in a reactor vessel, and the reactor core 1 is covered with a liquid metal sodium coolant 2 and has a fixed lid for closing the reactor vessel. An upper core mechanism 5 and a fuel exchanger 6 are installed at 3. Further, FIG. 1 shows a state at the time of refueling, in which an elevating coupler 7 is attached to the core upper part mechanism 5, and an elevating mechanism 8 and a guide cylinder 9 are provided.
Thus, a part of the core upper part mechanism 5 is pulled up.

【0015】炉心1は、図2に示すように六角柱状の燃
料集合体12および制御棒下部案内管13が蜂の巣状に
配置して構成され、この制御棒下部案内管13は制御棒
挿入孔としての円孔13aを設けた六角柱に形成され、
燃料集合体12はその内部に燃料ピンを内包する六角柱
であり、炉心1における燃料棒の発熱を除熱する冷却材
2が流れる構造になっている。そのため、燃料集合体1
2の頂部には、冷却材2の出口として円孔が形成されて
いる。
As shown in FIG. 2, the core 1 is constructed by arranging a hexagonal columnar fuel assembly 12 and a control rod lower guide tube 13 in a honeycomb shape, and the control rod lower guide tube 13 serves as a control rod insertion hole. Is formed into a hexagonal prism with a circular hole 13a,
The fuel assembly 12 is a hexagonal column containing a fuel pin therein, and has a structure in which a coolant 2 for removing heat generated by a fuel rod in the core 1 flows. Therefore, the fuel assembly 1
A circular hole is formed at the top of 2 as an outlet for the coolant 2.

【0016】この原子炉運転に必要な円孔を回避し、炉
心1の頂部、すなわち燃料集合体12と制御棒下部案内
管13の六角柱の隅角部にそれぞれ連結用凹部14を形
成する一方、炉心上部機構5の下端部に連結用凹部14
と嵌合する連結用凸部15が複数設けられている。
While avoiding the circular holes necessary for the operation of the reactor, connecting recesses 14 are formed at the top of the core 1, that is, at the corners of the hexagonal columns of the fuel assembly 12 and the lower control rod guide tube 13. , A connecting recess 14 at the lower end of the core upper mechanism 5.
There are provided a plurality of connecting convex portions 15 that fit with.

【0017】次に、本実施例の作用について説明する。Next, the operation of this embodiment will be described.

【0018】上記の構成において、炉心上部機構5の連
結用凸部15を炉心上部の連結用凹部14に嵌合させる
ことにより、炉心上部機構5の下端部が拘束される。そ
の結果、地震時に炉心上部機構5が固定蓋3のみの支持
による片持ち梁として振動することはなく、常に炉心上
部機構5の下端部は制御棒下部案内管13の頂部と水平
方向相対変位を生じることがなくなる。
In the above-mentioned structure, the lower end portion of the upper core mechanism 5 is restrained by fitting the connecting convex portion 15 of the upper core mechanism 5 into the connecting concave portion 14 of the upper core portion. As a result, the upper core mechanism 5 does not vibrate as a cantilever beam supported only by the fixed lid 3 during an earthquake, and the lower end of the upper core mechanism 5 always moves horizontally relative to the top of the lower control rod guide tube 13. It will never happen.

【0019】原子炉運転時や停止時、原子炉内の温度変
化により炉心上部機構5、炉心1およびその他の原子炉
構造に熱膨張差の相違が発生し、炉心上部機構5の下端
部と炉心1の頂部に軸方向変位が生じるが、この変位は
連結用凹部14内において連結用凸部15が摺動するこ
とにより吸収される。
A difference in thermal expansion occurs between the upper core mechanism 5, the core 1 and other structures of the reactor due to temperature changes in the reactor during operation or shutdown of the reactor, and the lower end of the upper core mechanism 5 and the core. An axial displacement is generated at the top of No. 1, but this displacement is absorbed by the sliding of the connecting projection 15 in the connecting recess 14.

【0020】また、燃料交換時は、図1に示すように炉
心上部機構5を引き上げると、連結用凸部15は炉心上
部機構5と同時に引き上げられるため、炉心上部は従来
の高速増殖炉と同様に燃料交換機6のグリッパ装置11
の作業空間として確保されることになる。
Further, at the time of refueling, when the core upper part mechanism 5 is pulled up as shown in FIG. 1, the connecting projection 15 is pulled up at the same time as the core upper part mechanism 5, so that the upper part of the core is similar to that of the conventional fast breeder reactor. The gripper device 11 of the refueling machine 6
Will be secured as a working space.

【0021】なお、上記実施例において、図2では炉心
上部機構5が1体の制御棒を案内して制御棒下部案内管
13に導く場合を示したが、これに限らず炉心上部機構
5が複数体の制御棒を案内するようにしてもよい。この
場合には、炉心上部機構5のそれぞれの制御棒案内孔の
下部に連結用凸部15を設置するようにすればよい。
In the above embodiment, FIG. 2 shows the case where the core upper mechanism 5 guides one control rod and guides it to the control rod lower guide tube 13. However, the core upper mechanism 5 is not limited to this. A plurality of control rods may be guided. In this case, the connecting projections 15 may be installed below the control rod guide holes of the core upper mechanism 5.

【0022】このように本実施例によれば、地震時に制
御棒の挿入を阻害する炉心上部機構5と制御棒下部案内
管13との水平方向相対変位はなくなり、地震時の制御
棒挿入性が著しく向上する。
As described above, according to this embodiment, the horizontal relative displacement between the upper core mechanism 5 and the lower control rod guide tube 13 which hinders the insertion of the control rod during an earthquake is eliminated, and the control rod insertability during an earthquake is improved. Remarkably improved.

【0023】図3は本実施例における第1変形例の主要
部である炉心上部機構の下端部および炉心の頂部の構造
を詳細に示す斜視図であり、既に説明した前記第1実施
例と同一または対応する部分には同一の符号を用いて説
明する。以下の各変形例および各実施例についても同様
である。
FIG. 3 is a perspective view showing in detail the structure of the lower end of the core upper part mechanism and the top of the core, which is the main part of the first modification of this embodiment, and is the same as that of the first embodiment already described. Alternatively, corresponding parts will be described using the same reference numerals. The same applies to the following modified examples and examples.

【0024】この第1変形例は、炉心1の制御棒下部案
内管13の頂部に形成した連結用凹部14をなくしたも
のである。すなわち、制御棒下部案内管13の頂部を円
筒形の構造とし、隣接する燃料集合体12との間に嵌合
用の空隙13bを形成する。この嵌合用の空隙13bに
嵌め合うように、炉心上部機構5の下端部に設けた嵌合
用凸部16の構造は略三角形状に形成されている。これ
ら嵌合用の空隙13bと嵌合用凸部16とで連結機構が
構成される。
In this first modification, the connecting recess 14 formed at the top of the control rod lower guide tube 13 of the core 1 is eliminated. That is, the top part of the control rod lower guide tube 13 has a cylindrical structure, and the space 13b for fitting is formed between the adjacent fuel assemblies 12. The fitting projection 16 provided at the lower end of the core upper mechanism 5 is formed into a substantially triangular shape so as to fit in the fitting space 13b. The fitting gap 13b and the fitting projection 16 constitute a connecting mechanism.

【0025】なお、図3に示す変形例では制御棒下部案
内管13の頂部のみを円筒形の構造とした場合を示した
が、制御棒下部案内管13の頂部および燃料集合体12
の頂部の双方を円筒形とするか、または燃料集合体12
の頂部のみを円筒形とし、炉心上部機構5の連結構造を
これと合致する形状に形成してもよい。
In the modification shown in FIG. 3, only the top of the control rod lower guide tube 13 has a cylindrical structure. However, the top of the control rod lower guide tube 13 and the fuel assembly 12 are shown.
Both of the tops of the cylinder are cylindrical or the fuel assembly 12
It is also possible to form only the top portion of the cylinder into a cylindrical shape and form the connection structure of the core upper part mechanism 5 in a shape matching this.

【0026】この第1変形例でも前記第1実施例と同様
の作用効果が得られる。その他の構成および効果は前記
第1実施例と同一であるのでその説明を省略する。
Also in this first modification, the same effects as those of the first embodiment can be obtained. Other configurations and effects are the same as those in the first embodiment, and therefore their explanations are omitted.

【0027】図4は第1実施例における第2変形例を示
し、この第2変形例は炉心上部機構5の下端部の連結構
造を嵌合フランジ17に変更したものである。制御棒下
部案内管13の頂部を燃料集合体7の頂部より低くする
ことで、炉心1の頂部に嵌合用の空間13cを形成す
る。
FIG. 4 shows a second modification of the first embodiment. In this second modification, the connecting structure of the lower end of the core upper mechanism 5 is changed to a fitting flange 17. By making the top of the control rod lower guide tube 13 lower than the top of the fuel assembly 7, a fitting space 13c is formed at the top of the core 1.

【0028】そして、炉心上部機構5の下端部は六角形
のフランジ構造とし、この嵌合フランジ17部分を炉心
1の頂部の嵌合用の空間13cに嵌合させることによ
り、炉心上部機構5の下端部と制御棒下部案内管13の
頂部とを連結する。その他の構成および効果は前記第1
実施例と同一であるのでその説明を省略する。
The lower end of the core upper mechanism 5 has a hexagonal flange structure, and the fitting flange 17 is fitted into the fitting space 13c at the top of the core 1 so that the lower end of the core upper mechanism 5 is fitted. And the top of the control rod lower guide tube 13 are connected. Other configurations and effects are the same as those in the first aspect.
The description is omitted because it is the same as the embodiment.

【0029】図5は第1実施例における第3変形例を示
し、この第3変形例は炉心1をダミー燃料集合体18を
含む構成に変更したものである。すなわち、この第3変
形例は炉心1内に燃料集合体および燃料棒下部案内管と
は異なり、炉心頂部の形状に原子炉運転などからくる、
例えば冷却材ナトリウムの流路や制御棒挿入孔の制約を
受けないダミー燃料集合体18を設置する。
FIG. 5 shows a third modification of the first embodiment, which is a modification of the core 1 including a dummy fuel assembly 18. That is, in this third modified example, unlike the fuel assembly and the fuel rod lower guide tube in the core 1, the shape of the core apex comes from the reactor operation, etc.
For example, a dummy fuel assembly 18 is installed that is not restricted by the coolant sodium flow path and the control rod insertion hole.

【0030】このダミー燃料集合体18の設置は、例え
ば核分裂反応などに関する炉心設計を変更することで実
施可能である。炉心上部機構5の下端には、ダミー燃料
集合体18の上部に連結する連結用凸部19を設置し、
この連結用凸部19をダミー燃料集合体18の頂部に嵌
合する。その他の構成および効果は前記第1実施例と同
一であるのでその説明を省略する。
The dummy fuel assembly 18 can be installed by changing the core design relating to, for example, fission reaction. At the lower end of the core upper part mechanism 5, a connecting projection 19 that is connected to the upper part of the dummy fuel assembly 18 is installed,
The connecting projection 19 is fitted on the top of the dummy fuel assembly 18. Other configurations and effects are the same as those in the first embodiment, and therefore their explanations are omitted.

【0031】図6は本発明の第2実施例における炉心上
部機構を含む高速増殖炉の縦断面図、図7(A),
(B)は図6の自在軸継手を示す縦断面図、図8
(A),(B)は図6の実施例の作用を示す説明図であ
る。
FIG. 6 is a longitudinal sectional view of a fast breeder reactor including an upper core mechanism according to the second embodiment of the present invention, FIG. 7 (A),
8B is a longitudinal sectional view showing the universal joint of FIG. 6, FIG.
(A), (B) is an explanatory view showing the operation of the embodiment of FIG.

【0032】この第2実施例は図6に示すように炉心上
部機構5の中間部に可撓性を有した自在軸継手20を設
けたものである。この軸継手20は図7(A),(B)
に示すように球面座21に対して球面軸22が所定角度
変位することで、炉心上部機構5の弓なりの変形を解消
し、制御棒下部案内管13の頂部との嵌合部における炉
心上部機構5と制御棒下部案内管13とのなす角度、す
なわち、制御棒が案内される孔の折れ曲がり角度を小さ
くするものである。
In the second embodiment, as shown in FIG. 6, a flexible universal joint 20 is provided in the middle portion of the core upper part mechanism 5. This shaft coupling 20 is shown in FIGS.
As shown in FIG. 4, the spherical shaft 22 is displaced by a predetermined angle with respect to the spherical seat 21, so that the bow-shaped deformation of the core upper part mechanism 5 is eliminated, and the core upper part mechanism at the fitting portion with the top part of the control rod lower guide tube 13 is eliminated. The angle formed by 5 and the control rod lower guide tube 13, that is, the bending angle of the hole through which the control rod is guided is reduced.

【0033】炉心上部機構5の上部は、原子炉容器の固
定蓋3により支持される一方、炉心1は原子炉容器の下
部から支持されているため、地震時にはこの両者は異な
るモードで振動する。
The upper part of the upper core mechanism 5 is supported by the fixed lid 3 of the reactor vessel, while the core 1 is supported from the lower part of the reactor vessel, so that both of them vibrate in different modes during an earthquake.

【0034】したがって、前記第1実施例のように炉心
上部機構5の下端部と、炉心1の頂部である制御棒下部
案内管13の頂部を嵌合させている場合、地震時には両
者の相対変位により、それを接続する炉心上部機構5は
図8(A)に示すように弓なりに変形する。ここで、炉
心上部機構5の上部に可撓性を有する自在軸継手20を
挿入した場合、図8(B)に示すように上記弓なりの変
形は解消される。
Therefore, when the lower end of the core upper mechanism 5 and the top of the control rod lower guide tube 13, which is the top of the core 1, are fitted to each other as in the first embodiment, the relative displacement between the two is caused during an earthquake. As a result, the core upper part mechanism 5 connecting them is deformed into a bow shape as shown in FIG. 8 (A). Here, when the flexible universal joint 20 having flexibility is inserted into the upper part of the core upper part mechanism 5, the above-mentioned bow-like deformation is eliminated as shown in FIG. 8B.

【0035】また、自在軸継手20を設けた場合と設け
ない場合とを比較すると、図8(A),(B)に示すよ
うに炉心1と固定蓋3の水平変位が同一である場合、制
御棒が通過する炉心上部機構5と制御棒下部案内管8の
つなぎ目の角度は、継手を設けた場合の方が小さくなる
(角度a>b)。
Further, comparing the case where the universal shaft coupling 20 is provided and the case where it is not provided, as shown in FIGS. 8A and 8B, when the horizontal displacement of the core 1 and the fixed lid 3 is the same, The angle at the joint between the core upper mechanism 5 and the control rod lower guide tube 8 through which the control rod passes is smaller when the joint is provided (angle a> b).

【0036】すなわち、炉心上部機構5の上下で水平方
向相対変位が生ずると、球面軸22は球面座21上をす
べり、これによって炉心上部機構5は継手部分で折れ曲
がり変形を起こす。その結果、炉心上部機構5の下端と
炉心1の頂部のなす角度は軸継手20が弓なり変形によ
る場合より小さいものとなる。
That is, when horizontal relative displacement occurs above and below the upper core mechanism 5, the spherical shaft 22 slides on the spherical seat 21, which causes the upper core mechanism 5 to bend and deform at the joint portion. As a result, the angle formed by the lower end of the core upper mechanism 5 and the top of the core 1 is smaller than that when the shaft coupling 20 is bowed.

【0037】したがって、地震時にここを通過する制御
棒にとって3点当たりなどによる挿入を阻害する要因が
減少し、制御棒の挿入性が一段と向上する。
Therefore, the factors that hinder the insertion of the control rod, such as hitting at three points, for the control rod passing therethrough during an earthquake are reduced, and the insertability of the control rod is further improved.

【0038】図9は本発明の第3実施例における炉心上
部機構を含む高速増殖炉の縦断面図である。この第3実
施例は炉心上部機構5を周方向に囲む円筒体30が固定
蓋3の底面に設置されており、円筒体30の下部には支
持部材としての水平支持板31が取り付けられている。
FIG. 9 is a longitudinal sectional view of a fast breeder reactor including an upper core mechanism according to the third embodiment of the present invention. In the third embodiment, a cylindrical body 30 surrounding the core upper mechanism 5 in the circumferential direction is installed on the bottom surface of the fixed lid 3, and a horizontal support plate 31 as a supporting member is attached to the lower portion of the cylindrical body 30. .

【0039】したがって、炉心上部機構5の中間部を水
平支持板31で支持することにより、地震時に炉心上部
機構5が固定蓋3で支持された片持ち梁として振動する
のではなく、水平支持板31の支持部から下端までの長
さの片持ち梁と同等の振動となるため、地震時の変位は
低減される。
Therefore, by supporting the middle portion of the core upper part mechanism 5 by the horizontal support plate 31, the core upper part mechanism 5 does not vibrate as a cantilever supported by the fixed lid 3 at the time of an earthquake, but the horizontal support plate 31. Since the vibration is equivalent to that of a cantilever having a length from the supporting portion 31 to the lower end, the displacement during an earthquake is reduced.

【0040】燃料交換時、図10に示すように炉心上部
機構5は、引き上げられるが、円筒体30および水平支
持板31は、燃料交換機6の作動範囲外にあるため、交
換作業空間は確保される。
At the time of refueling, as shown in FIG. 10, the core upper part mechanism 5 is pulled up, but since the cylindrical body 30 and the horizontal support plate 31 are out of the operating range of the refueling machine 6, a replacement work space is secured. It

【0041】図11は第3実施例における変形例を示
し、この変形例では第3実施例の円筒体30および水平
支持板31に加え、炉心上部機構5の下端部に分割水平
板32を設け、この水平板32同志が嵌合用部材により
嵌合されたものである。
FIG. 11 shows a modification of the third embodiment. In this modification, a split horizontal plate 32 is provided at the lower end of the core upper mechanism 5 in addition to the cylindrical body 30 and the horizontal support plate 31 of the third embodiment. The horizontal plates 32 are fitted together by a fitting member.

【0042】したがって、この変形例によれば、分割水
平板32同志を連結させることにより、剛性を一段と高
めることができ、地震時の変位をさらに低減させること
ができる。
Therefore, according to this modification, by connecting the divided horizontal plates 32 to each other, the rigidity can be further enhanced and the displacement during an earthquake can be further reduced.

【0043】[0043]

【発明の効果】以上説明したように、本発明の請求項1
によれば、炉心上部機構の下端部が炉心の頂部に連結さ
れているため、これら両者は地震時においても同一の変
位が生じ、炉心上部機構の制御棒案内孔と炉心の制御棒
挿入孔との水平方向相対変位をなくすことが可能とな
る。その結果、地震時の制御棒挿入性が向上し、地震時
の原子炉の停止がより確実となり、安全性が高まる。
As described above, according to the first aspect of the present invention.
According to the above, since the lower end of the core upper part mechanism is connected to the top part of the core, the same displacement occurs even during an earthquake, and the control rod guide hole of the core upper part mechanism and the control rod insertion hole of the core are It is possible to eliminate the relative displacement in the horizontal direction. As a result, the control rod insertability at the time of an earthquake is improved, the shutdown of the reactor at the time of an earthquake becomes more reliable, and the safety is enhanced.

【0044】また、請求項2においては、炉心上部機構
の中間部が炉心上部機構を囲む筒体に設けた支持部材に
より支持されるため、地震時においても炉心上部機構の
下端部の変形が低減され、炉心の制御棒挿入孔との水平
方向相対変位が低減可能となる。これにより、請求項1
と同様に地震時の制御棒挿入性が向上し、地震時の原子
炉の停止がより確実となり、安全性が高まる。
Further, according to the present invention, since the intermediate portion of the core upper part mechanism is supported by the supporting member provided in the cylindrical body surrounding the core upper part mechanism, the deformation of the lower end part of the core upper part mechanism is reduced even during an earthquake. Therefore, the horizontal relative displacement of the core with respect to the control rod insertion hole can be reduced. Thereby, claim 1
Similarly to the above, the control rod insertability at the time of the earthquake is improved, the shutdown of the reactor at the time of the earthquake becomes more reliable, and the safety is improved.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明の第1実施例における炉心上部機構を含
む高速増殖炉の縦断面図。
FIG. 1 is a vertical sectional view of a fast breeder reactor including an upper core mechanism according to a first embodiment of the present invention.

【図2】図1における実施例の主要部である炉心上部機
構の下端部および炉心の頂部の構造を詳細に示す斜視
図。
FIG. 2 is a perspective view showing in detail the structures of the lower end portion of the core upper part mechanism and the top portion of the core, which are the main parts of the embodiment in FIG.

【図3】第1実施例における第1変形例の主要部である
炉心上部機構の下端部および炉心の頂部の構造を詳細に
示す斜視図。
FIG. 3 is a perspective view showing in detail the structures of the lower end portion of the core upper part mechanism and the top portion of the core, which are the main parts of the first modification example of the first embodiment.

【図4】第1実施例における第2変形例の主要部である
炉心上部機構の下端部および炉心の頂部の構造を詳細に
示す斜視図。
FIG. 4 is a perspective view showing in detail the structures of the lower end portion of the core upper part mechanism and the top portion of the core, which are the main parts of the second modification example of the first embodiment.

【図5】第1実施例における第3変形例を示す炉心上部
機構を含む高速増殖炉の縦断面図。
FIG. 5 is a vertical cross-sectional view of a fast breeder reactor including a core upper part mechanism showing a third modified example of the first embodiment.

【図6】本発明の第2実施例における炉心上部機構を含
む高速増殖炉の縦断面図。
FIG. 6 is a vertical cross-sectional view of a fast breeder reactor including a core upper part mechanism according to a second embodiment of the present invention.

【図7】(A),(B)は図6の自在軸継手を示す縦断
面図。
7 (A) and 7 (B) are vertical sectional views showing the universal joint of FIG. 6.

【図8】(A),(B)は図6の実施例の作用を示す説
明図。
8A and 8B are explanatory views showing the operation of the embodiment of FIG.

【図9】本発明の第3実施例における炉心上部機構を含
む高速増殖炉の縦断面図。
FIG. 9 is a vertical cross-sectional view of a fast breeder reactor including a core upper part mechanism according to a third embodiment of the present invention.

【図10】図9において燃料交換時に炉心上部機構を引
き上げた状態を示す縦断面図。
10 is a vertical cross-sectional view showing a state in which the core upper part mechanism is pulled up at the time of refueling in FIG.

【図11】第3実施例における変形例を示す炉心上部機
構を含む高速増殖炉の縦断面図。
FIG. 11 is a vertical cross-sectional view of a fast breeder reactor including an upper core mechanism showing a modification of the third embodiment.

【図12】従来例における炉心上部機構を含む高速増殖
炉の縦断面図。
FIG. 12 is a vertical cross-sectional view of a fast breeder reactor including an upper core mechanism in a conventional example.

【図13】図12において燃料交換時に炉心上部機構を
引き上げた状態を示す縦断面図。
FIG. 13 is a vertical cross-sectional view showing a state in which the core upper part mechanism is pulled up at the time of refueling in FIG.

【符号の説明】[Explanation of symbols]

1 炉心 2 冷却材 3 固定蓋 4 制御棒駆動機構 5 炉心上部機構 12 燃料集合体 13 制御棒下部案内管 13a 円孔(制御棒挿入孔) 14 連結用凹部(連結機構) 15 連結用凸部(連結機構) 20 自在軸継手 21 球面座 22 球面軸 30 円筒体(筒体) 31 水平支持板(支持部材) 32 分割水平板 DESCRIPTION OF SYMBOLS 1 core 2 coolant 3 fixed lid 4 control rod drive mechanism 5 core upper mechanism 12 fuel assembly 13 control rod lower guide tube 13a circular hole (control rod insertion hole) 14 connection recess (connection mechanism) 15 connection projection ( Coupling mechanism) 20 Universal shaft joint 21 Spherical seat 22 Spherical shaft 30 Cylindrical body (cylindrical body) 31 Horizontal support plate (support member) 32 Divided horizontal plate

フロントページの続き (72)発明者 神保 雅一 神奈川県横浜市磯子区新杉田町8番地 株 式会社東芝横浜事業所内Front Page Continuation (72) Inventor Masakazu Jimbo 8 Shinsita-cho, Isogo-ku, Yokohama-shi, Kanagawa Stock Company Toshiba Yokohama Office

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】 原子炉容器内に収容された炉心と、この
炉心の制御棒挿入孔に制御棒を案内する制御棒案内孔を
設けた炉心上部機構とを有し、この炉心上部機構を引き
上げて燃料交換を行う高速増殖炉において、上記炉心の
頂部と上記炉心上部機構の下端部とを連結する連結機構
を設けたことを特徴とする高速増殖炉。
1. A core housed in a nuclear reactor vessel, and a core upper mechanism having a control rod guide hole for guiding a control rod into a control rod insertion hole of the core, and the core upper mechanism is pulled up. A fast breeder reactor for exchanging fuel by providing a connecting mechanism for connecting the top part of the core and the lower end part of the core upper part mechanism.
【請求項2】 原子炉容器内に収容された炉心と、この
炉心の制御棒挿入孔に制御棒を案内する制御棒案内孔を
設けた炉心上部機構とを有し、この炉心上部機構を引き
上げて燃料交換を行う高速増殖炉において、上記炉心上
部機構を囲む筒体を設け、この筒体に上記炉心上部機構
の中間部を支持する支持部材を設けたことを特徴とする
高速増殖炉。
2. A core housed in a nuclear reactor vessel, and a core upper mechanism having a control rod guide hole for guiding a control rod into a control rod insertion hole of the core, and the core upper mechanism is pulled up. A fast breeder reactor for exchanging fuel by providing a tubular body surrounding the upper core mechanism, and providing a supporting member for supporting an intermediate portion of the upper core mechanism in the tubular body.
JP5114821A 1993-05-17 1993-05-17 Fast breeder reactor Pending JPH06324188A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP5114821A JPH06324188A (en) 1993-05-17 1993-05-17 Fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP5114821A JPH06324188A (en) 1993-05-17 1993-05-17 Fast breeder reactor

Publications (1)

Publication Number Publication Date
JPH06324188A true JPH06324188A (en) 1994-11-25

Family

ID=14647532

Family Applications (1)

Application Number Title Priority Date Filing Date
JP5114821A Pending JPH06324188A (en) 1993-05-17 1993-05-17 Fast breeder reactor

Country Status (1)

Country Link
JP (1) JPH06324188A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112331368A (en) * 2020-11-05 2021-02-05 启迪新核(北京)能源科技有限公司 Reactor core

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112331368A (en) * 2020-11-05 2021-02-05 启迪新核(北京)能源科技有限公司 Reactor core

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