JPH04132994A - Fast breeder reactor - Google Patents

Fast breeder reactor

Info

Publication number
JPH04132994A
JPH04132994A JP2256149A JP25614990A JPH04132994A JP H04132994 A JPH04132994 A JP H04132994A JP 2256149 A JP2256149 A JP 2256149A JP 25614990 A JP25614990 A JP 25614990A JP H04132994 A JPH04132994 A JP H04132994A
Authority
JP
Japan
Prior art keywords
control rod
drive mechanism
rod drive
reactor
roof slab
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
JP2256149A
Other languages
Japanese (ja)
Inventor
Shigeru Adachi
茂 足立
Takuo Miyagi
宮城 卓穂
Hiroto Kawakami
川上 博人
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 JP2256149A priority Critical patent/JPH04132994A/en
Publication of JPH04132994A publication Critical patent/JPH04132994A/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

Abstract

PURPOSE:To enable refueling without a rotary plug by making a control rod drive mechanism and a guide tube of the control rod drive mechanism, to be of retractable structure and also by making a supporting table of the control rod drive mechanism guide tube, to be able to be housed in the vicinity underneath a roof slab, freely to its telescopic movement. CONSTITUTION:Inside a nuclear reactor vessel 11, a reactor core 12, a reactor core supporting structure 13, a supporting table 21 of the control rod drive mechanism guide tube, a supporting mechanism 22 which supports and moves vertically the supporting plate 21, and the like, are housed in. To a roof slab 19 constituting a lid of the vessel 11, a control rod drive mechanism 15 is attached freely detachably and re-attachably. For refueling, the mechanism 15 is detached, the supporting plate 21 is housed in the vicinity of an underside surface of the roof slab 19 by the mechanism 22 and an arm typed refueling machine is set up at the center of the roof slab 19. By this whole constitution, new and spent fuels can be exchanged without using a rotary plug, and the similar works can be done as well.

Description

【発明の詳細な説明】 [発明の目的コ (産業上の利用分野) 本発明は、冷却材として液体金属を利用する高速増殖炉
に関するもので、特に回転プラグを省(することによっ
て、直径の小さな原子炉容器で構成できる高速増殖炉に
関する。
Detailed Description of the Invention [Purpose of the Invention (Industrial Application Field) The present invention relates to a fast breeder reactor that uses liquid metal as a coolant. This invention relates to a fast breeder reactor that can be constructed from a small reactor vessel.

(従来の技術) 従来の高速増殖炉は、第3図に示すように、原子炉容器
11内に、炉心12、炉心支持構造物13、炉心上部機
構14、制御棒駆動機構15、燃料交換機16、中間熱
交換器17、および1次主循環ポンプ18を内包し、原
子炉容器11の上端は、ルーフスラブ19と回転プラグ
20から成る蓋によって閉塞されている。
(Prior Art) As shown in FIG. 3, a conventional fast breeder reactor includes a reactor core 12, a core support structure 13, a core upper mechanism 14, a control rod drive mechanism 15, and a fuel exchanger 16 in a reactor vessel 11. , an intermediate heat exchanger 17, and a primary main circulation pump 18, and the upper end of the reactor vessel 11 is closed by a lid consisting of a roof slab 19 and a rotating plug 20.

回転プラグ20はルーフスラブ19に回転可能に搭載さ
れ、また、制御棒駆動機構15は、回転プラグ20に取
付けられた炉心上部機構14によって収納・支持・位置
決めされる。
The rotating plug 20 is rotatably mounted on the roof slab 19, and the control rod drive mechanism 15 is accommodated, supported, and positioned by the core upper mechanism 14 attached to the rotating plug 20.

このような構成の高速増殖炉において、炉心12で発生
する熱量は、制御棒駆動機構15のグリッパにより、上
端部のハンドリングヘッドを掴まれた制御棒を上下に動
かすことによって制御される。
In a fast breeder reactor with such a configuration, the amount of heat generated in the core 12 is controlled by a gripper of a control rod drive mechanism 15 that moves the control rods gripped by the handling head at the upper end up and down.

一方、高速増殖炉の燃料交換を行う際には、制御棒を全
て炉心へ挿入した後、制御棒駆動機構15のグリッパで
掴んでいた制御棒を切離し、制御棒駆動機構15のグリ
ッパを少し上に移動させ、炉心12と炉心上部機構14
側の結合を解く。このようにして炉心上部機構14を搭
載した回転プラグ20を回転可能な状態にした後、燃料
交換機16と回転プラグ20の回転動により、炉心部に
あって交換を必要とされる燃料集合体のハンドリングヘ
ッド部を燃料交換機のグリッパで掴み、燃料集合体を上
方向に持上げ、炉心部から完全に弓抜いた後、回転プラ
グの回転と燃料交換機に具備された回転機能とにより炉
内の所定位置(炉内中継位置)まで水平方向に移動させ
、その場所において下方向に燃料集合体を降ろした後、
掴んでいた燃料集合体を切離す。
On the other hand, when exchanging fuel in a fast breeder reactor, after inserting all the control rods into the reactor core, the control rods gripped by the grippers of the control rod drive mechanism 15 are separated, and the grippers of the control rod drive mechanism 15 are moved slightly upward. The reactor core 12 and the upper core mechanism 14 are moved to
Untie the sides. After the rotary plug 20 equipped with the core upper mechanism 14 is made rotatable in this manner, the rotation of the fuel exchanger 16 and the rotary plug 20 causes the fuel assemblies in the reactor core that require replacement to be removed. Grasp the handling head part with the gripper of the fuel exchanger, lift the fuel assembly upward, and after completely removing the bow from the reactor core, use the rotation of the rotary plug and the rotation function of the fuel exchanger to move it to a predetermined position inside the reactor. After moving the fuel assembly horizontally to the relay position in the reactor and lowering the fuel assembly downward at that location,
Separate the fuel assembly that was being held.

次に、同じ炉内中継位置において新燃料集合体を掴み、
丁度、上記と逆の操作をすることにより新燃料集合体を
炉心部に装荷する。
Next, grab the new fuel assembly at the same relay position in the reactor,
A new fuel assembly is loaded into the reactor core by performing exactly the opposite operation to the above.

以上の操作を繰返すことにより、高速増殖炉の燃料交換
を行うことができるが、その要点は、制御棒駆動機構1
5で掴んでいた制御棒を切離し、制御棒駆動機構15を
収納・支持・位置決めしている炉心上部機構14を回転
プラグ20て移動させ、燃料交換のために必要な炉心部
上方の空間を確保することにある。
By repeating the above operations, fuel exchange of the fast breeder reactor can be performed, but the main point is that the control rod drive mechanism 1
Separate the control rods held by 5 and move the upper core mechanism 14 that accommodates, supports, and positions the control rod drive mechanism 15 using the rotary plug 20 to secure the space above the core necessary for fuel exchange. It's about doing.

なお、燃料交換のための回転プラグ20の種類としては
、単回転プラグ、2重回転プラグ、あるいは3重回転プ
ラグがあり、また燃料交換機16としては、アーム式燃
料交換機、直動式燃料交換機、アーム式と直動式燃料交
換機の併用、または直動式燃料交換機2基使用なども考
えられる。
The types of rotary plugs 20 for fuel exchange include single rotation plugs, double rotation plugs, and triple rotation plugs, and the fuel exchange machines 16 include arm-type fuel exchange machines, direct-acting fuel exchange machines, It is also possible to use an arm type and a direct-acting fuel exchanger together, or to use two direct-acting fuel exchangers.

しかしながら、上述したような回転プラグと燃料交換機
の組合わせによる燃料交換システムにおいては、炉上部
配置、すなわち、ルースフラグ19と回転プラグ20の
配置を考えると、回転プラグ20は回転機構装置や回転
部シール装置、遮蔽構造、および動力用・計測制御用の
ケーブル類等が必要となり、径方向の寸法も大きなスペ
ースを占め、原子炉容器11の直径を決める上でのクリ
ティカル要因の一つとなっている。
However, in a fuel exchange system using a combination of a rotary plug and a fuel exchanger as described above, considering the arrangement in the upper part of the furnace, that is, the arrangement of the loose flag 19 and the rotary plug 20, the rotary plug 20 is not connected to the rotating mechanism device or the rotating part. Seal devices, shielding structures, cables for power and measurement control, etc. are required, and the radial dimension also occupies a large space, which is one of the critical factors in determining the diameter of the reactor vessel 11. .

(発明が解決しようとする課題) 以上説明したように、回転プラグ20と燃料交換機16
からなる燃料交換システムを採用した従来の高速増殖炉
においては、原子炉容器11の直径が大きくなる傾向が
あり、回転プラグ回りの寸法関係が原子炉容器11の直
径のクリティカル要因の一つとなっていた。
(Problem to be Solved by the Invention) As explained above, the rotary plug 20 and the fuel exchanger 16
In conventional fast breeder reactors that employ a fuel exchange system consisting of Ta.

本発明は上記の点の鑑みて成されたもので、回転プラグ
がなくても燃料交換を行なえるシステムを採用すること
によって、直径の小さな原子炉容器で構成できる高速増
殖炉を提供することを目的とするものである。
The present invention has been made in view of the above points, and aims to provide a fast breeder reactor that can be configured with a reactor vessel having a small diameter by adopting a system that allows fuel exchange without a rotating plug. This is the purpose.

[発明の構成] (課題を解決するための手段) 本発明の高速増殖炉は、原子炉容器と、その中に収納さ
れた炉心および炉心支持構造物と、前記原子炉容器の蓋
を構成するルーフスラブとを備えた高速増殖炉において
、前記ルーフスラブには回転プラグを設けることなく、
制御棒駆動機構および制御棒駆動機構案内管を弓゛1抜
き可能な構造として選択的に設置し、前記制御棒駆動機
構案内管を支持する支持板を、伸縮自在の支持機構を介
して前記ルーフスラブの下面近傍に収納可能としたこと
を特徴とする。
[Structure of the Invention] (Means for Solving the Problems) The fast breeder reactor of the present invention comprises a reactor vessel, a reactor core and a core support structure housed therein, and a lid of the reactor vessel. In a fast breeder reactor equipped with a roof slab, the roof slab is not provided with a rotating plug,
The control rod drive mechanism and the control rod drive mechanism guide tube are selectively installed as a structure that allows the bow to be pulled out, and the support plate supporting the control rod drive mechanism guide tube is attached to the roof via a telescopic support mechanism. It is characterized by being able to be stored near the bottom surface of the slab.

(作用) 上記の構成を採用した場合、原子炉出力運転時にはルー
フスラブに搭載された制御棒駆動機構により制御棒の炉
心部への挿入、引抜き操作が行なえる。また地震時等に
おける制御棒駆動機構の機能健全性を保つ上では、制御
棒駆動機構案内管支持板が有効である。
(Function) When the above configuration is adopted, the control rod drive mechanism mounted on the roof slab allows the control rods to be inserted into and withdrawn from the reactor core during reactor power operation. Furthermore, the control rod drive mechanism guide tube support plate is effective in maintaining the functional integrity of the control rod drive mechanism during earthquakes and the like.

また、燃料交換時には制御棒駆動機構を全て取外し、伸
縮自在の支持機構を縮めることによって制御棒駆動機構
案内管支持板をルーフスラブ下面近傍に収納し、炉心上
方に燃料交換のための必要スペースを確保する。
In addition, when replacing fuel, the entire control rod drive mechanism is removed and the telescoping support mechanism is retracted to accommodate the control rod drive mechanism guide tube support plate near the bottom of the roof slab, freeing up the necessary space above the core for fuel exchange. secure.

その状態で、炉心中心真上、すなわちルーフスラブ中心
にアーム式燃料交換機を設置して燃料交換を行う。
In this state, an arm-type refueling machine is installed directly above the center of the reactor core, that is, at the center of the roof slab, to perform fuel exchange.

(実施例) 次に、図面を参照しながら本発明の実施例を説明する。(Example) Next, embodiments of the present invention will be described with reference to the drawings.

なお、第1図および第2図において、第3図におけると
同一部分には同一符号を付し、同一部分の説明は省略す
る。
Note that in FIGS. 1 and 2, the same parts as in FIG. 3 are given the same reference numerals, and explanations of the same parts will be omitted.

第1図は本発明の一実施例を示すもので、同図(a)は
原子炉出力運転時の状態を示し、同図(b)は燃料交換
時の状態を示す。
FIG. 1 shows an embodiment of the present invention. FIG. 1(a) shows the state during reactor power operation, and FIG. 1(b) shows the state during fuel exchange.

第1図(a)、(b)から明らかなように、本発明の高
速増殖炉では、従来の回転プラグ20(第3図)は使用
されず、原子炉容器11の上端は、全面をルーフスラブ
19によって覆われている。
As is clear from FIGS. 1(a) and (b), in the fast breeder reactor of the present invention, the conventional rotating plug 20 (FIG. 3) is not used, and the upper end of the reactor vessel 11 is covered with a roof. Covered by slab 19.

第1図(a)において、原子炉容器11内には炉心12
、炉心支持構造物13、中間熱交換器17.1次主循環
ポンプ18、制御棒駆動機構案内管支持板21、および
この案内管支持板21を支持すると共に上下動させる支
持機構22が収納されている。
In FIG. 1(a), there is a reactor core 12 inside the reactor vessel 11.
, a core support structure 13, an intermediate heat exchanger 17, a primary main circulation pump 18, a control rod drive mechanism guide tube support plate 21, and a support mechanism 22 that supports the guide tube support plate 21 and moves it up and down. ing.

原子炉容器11の蓋を構成するルーフスラブ19には、
制御棒駆動機構15が着脱自在に取付けられている。
The roof slab 19 that constitutes the lid of the reactor vessel 11 includes:
A control rod drive mechanism 15 is detachably attached.

支持機構22は、例えばテレスコープ型の複数本の支持
バイブから構成されている。
The support mechanism 22 includes, for example, a plurality of telescope-type support vibes.

一方、燃料交換時には、第1図(b)に示すように、制
御棒駆動機構15を取外し、支持機構22によって、制
御棒駆動機構案内管支持板21をルーフスラブ19下面
近傍に収納し、ルーフスラブ19の中央にアーム式燃料
交換機16を設置する。
On the other hand, at the time of fuel exchange, as shown in FIG. An arm type fuel exchanger 16 is installed in the center of the slab 19.

上述した本発明の高速増殖炉においては、回転プラグを
使用せずとも、原子炉出力運転時での制御棒と制御棒駆
動機構による炉心出力の調整機能と、地震時等における
制御棒の機能健全性を満たせることは勿論、燃料交換時
においても新旧燃料の交換を支障なく行うことができる
In the fast breeder reactor of the present invention described above, the control rods and the control rod drive mechanism can adjust the core output during reactor power operation and maintain the functional integrity of the control rods during earthquakes, etc., without using a rotating plug. In addition to meeting the requirements, it is also possible to exchange old and new fuel without any problems during fuel exchange.

その結果、原子炉容器の直径を決める上でのクリティカ
ル要因の一つである炉上部配置の制約を解消でき、小径
化した原子炉容器を備えた高速増殖炉を供給することが
できる。
As a result, restrictions on the upper reactor arrangement, which is one of the critical factors in determining the diameter of the reactor vessel, can be resolved, and a fast breeder reactor equipped with a reactor vessel having a reduced diameter can be provided.

また回転プラグをなくすことにより、回転プラグを使用
する場合に必要であった回転機構類、回転部ジャーナル
、遮蔽、およびケーブル類をなくすこともでき、炉上部
配置の簡素化にも大きな効果がある。
Also, by eliminating the rotating plug, it is possible to eliminate the rotating mechanisms, rotating journals, shields, and cables that are required when using a rotating plug, which has a great effect on simplifying the furnace top arrangement. .

なお、本発明においては、第2図に示すように制御棒駆
動機構15と、燃料交換機16(第1図(b))を設置
するルーフスラブ19の中央部分を、それとは別体構造
物とし、回転機能を持たせない炉上部プラグ23として
もよい。その場合には、制御棒駆動機構案内管支持板2
1と、その支持機構22をルーフスラブから容易に取外
すことができ、万一の故障等に対しても対策が容易とな
る。
In addition, in the present invention, as shown in FIG. 2, the central part of the roof slab 19 on which the control rod drive mechanism 15 and the fuel exchanger 16 (FIG. 1(b)) are installed is a separate structure. , the furnace upper plug 23 may have no rotation function. In that case, the control rod drive mechanism guide tube support plate 2
1 and its support mechanism 22 can be easily removed from the roof slab, making it easy to take measures against any unexpected failures.

また、第1図(a)、(b)に示す実施例においては、
アーム式燃料交換機16をルーフスラブ19中夫に1基
のみ搭載したが、大型炉のように炉心部の径が大きい場
合には、制御棒駆動機構15の外周部に複数基のアーム
式燃料交換機16をおくことも可能である。
Furthermore, in the embodiment shown in FIGS. 1(a) and (b),
Although only one arm-type fuel exchanger 16 is mounted on the roof slab 19, in the case of a large reactor with a large diameter core, multiple arm-type fuel exchangers may be installed on the outer periphery of the control rod drive mechanism 15. It is also possible to set 16.

[発明の効果コ 上述のように、本発明によれば、回転プラグを使用せず
とも、ルーフスラブに搭載された制御棒駆動機構により
制御棒の炉心部への挿入、引抜き操作を支障なく行うこ
とができ、直径の小さな原子炉容器で高速増殖炉を構成
することができる。
[Effects of the Invention] As described above, according to the present invention, the control rod drive mechanism mounted on the roof slab allows the control rods to be inserted into and withdrawn from the reactor core without any trouble, without using a rotating plug. It is possible to construct a fast breeder reactor using a reactor vessel with a small diameter.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図(a)、(b)は本発明に係わる高速増殖炉の実
施例の縦断面図であって、第1図(a)は原子炉出力運
転時の状態を示し、同図(b)は燃料交換時の状態を示
す。第2図は本発明の他の実施例を示す縦断面図、第3
図は従来の高速増殖炉の縦断面図を示す。 11・・・・・・原子炉容器 12・・・・・・炉心 13・・・・・・炉心支持構造物 14・・・・・・炉心上部機構 15・・・・・・制御棒駆動機構 16・・・・・・燃料交換機 17・・・・・・中間熱交換器 18・・・・・・1次主循環ポンプ 19・・・・・・ルーフスラブ 20・・・・・・回転プラグ 21 ・・ ・・・支持板 22・・・・・・支持機構 23・・・・・・炉上部プラグ
FIGS. 1(a) and 1(b) are longitudinal cross-sectional views of an embodiment of the fast breeder reactor according to the present invention, in which FIG. 1(a) shows the state during reactor power operation, and FIG. ) indicates the condition at the time of fuel exchange. FIG. 2 is a vertical sectional view showing another embodiment of the present invention, and FIG.
The figure shows a longitudinal cross-sectional view of a conventional fast breeder reactor. 11... Reactor vessel 12... Core 13... Core support structure 14... Core upper mechanism 15... Control rod drive mechanism 16... Fuel exchanger 17... Intermediate heat exchanger 18... Primary main circulation pump 19... Roof slab 20... Rotating plug 21...Support plate 22...Support mechanism 23...Furnace upper plug

Claims (1)

【特許請求の範囲】[Claims] 原子炉容器と、その中に収納された炉心および炉心支持
構造物と、前記原子炉容器の蓋を構成するルーフスラブ
とを備えた高速増殖炉において、前記ルーフスラブには
、回転プラグを設けることなく、制御棒駆動機構および
制御棒駆動機構案内管を引抜き可能な構造として選択的
に設置し、前記制御棒駆動機構案内管を支持する支持板
を、伸縮自在の支持機構を介して前記ルーフスラブの下
面近傍に収納可能としたことを特徴とする高速増殖炉。
In a fast breeder reactor comprising a reactor vessel, a reactor core and a core support structure housed therein, and a roof slab forming a lid of the reactor vessel, the roof slab may be provided with a rotating plug. The control rod drive mechanism and the control rod drive mechanism guide tube are selectively installed as a removable structure, and the support plate supporting the control rod drive mechanism guide tube is attached to the roof slab through a telescoping support mechanism. A fast breeder reactor characterized in that it can be stored near the bottom surface of the reactor.
JP2256149A 1990-09-26 1990-09-26 Fast breeder reactor Pending JPH04132994A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2256149A JPH04132994A (en) 1990-09-26 1990-09-26 Fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2256149A JPH04132994A (en) 1990-09-26 1990-09-26 Fast breeder reactor

Publications (1)

Publication Number Publication Date
JPH04132994A true JPH04132994A (en) 1992-05-07

Family

ID=17288588

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2256149A Pending JPH04132994A (en) 1990-09-26 1990-09-26 Fast breeder reactor

Country Status (1)

Country Link
JP (1) JPH04132994A (en)

Similar Documents

Publication Publication Date Title
US4056435A (en) Loading and unloading of a nuclear reactor core
JP5734543B2 (en) Refueling assembly for nuclear reactors
US4096031A (en) Nuclear reactor refueling system
EP2948958B1 (en) Nuclear fuel assembly handling apparatus
JPH04132994A (en) Fast breeder reactor
WO2020149567A1 (en) Apparatus and method for decommissioning heavy-water reactor facility
JP2856864B2 (en) Fast breeder reactor
JPH04268494A (en) Fast breeder reactor
JPH06235791A (en) Fast breeder reactor
EP0240602A2 (en) Fuel transfer means
JPS60187896A (en) Charger for fuel
US4705661A (en) Fast neutron nuclear reactor equipped with a central handling cell and a boxed slab
JPH02161394A (en) Refueling device
JPH0540197A (en) Refueling method for reactor
JP3028678B2 (en) Reactor upper mechanism of fast breeder reactor
JPH06235783A (en) Fast breeder reactor
JPS6227918Y2 (en)
JP2660465B2 (en) Fast reactor refueling equipment
JPH03259798A (en) Refueling device for nuclear reactor
JPS6122798B2 (en)
JPH02281199A (en) Refuelling device for nuclear reactor
JPS6367594A (en) Fast breeder reactor
JPS60162995A (en) Nuclear reactor
JPS595996A (en) Fuel exchanging device
JPS63214690A (en) Nuclear reactor