JPS58161882A - Fast breeder reactor - Google Patents

Fast breeder reactor

Info

Publication number
JPS58161882A
JPS58161882A JP57044182A JP4418282A JPS58161882A JP S58161882 A JPS58161882 A JP S58161882A JP 57044182 A JP57044182 A JP 57044182A JP 4418282 A JP4418282 A JP 4418282A JP S58161882 A JPS58161882 A JP S58161882A
Authority
JP
Japan
Prior art keywords
reactor
core
control rod
drive mechanism
rod drive
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
JP57044182A
Other languages
Japanese (ja)
Inventor
「たる」谷 耕平
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
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Nippon Genshiryoku Jigyo KK
Tokyo Shibaura Electric Co Ltd
Nippon Atomic Industry Group Co Ltd
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 Nippon Genshiryoku Jigyo KK, Tokyo Shibaura Electric Co Ltd, Nippon Atomic Industry Group Co Ltd filed Critical Nippon Genshiryoku Jigyo KK
Priority to JP57044182A priority Critical patent/JPS58161882A/en
Publication of JPS58161882A publication Critical patent/JPS58161882A/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

  • Heat-Exchange Devices With Radiators And Conduit Assemblies (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】 〔発明の技術分野〕 本発明は地振発生時等においても炉出力の制御が正常に
行なわれるようにした高速増殖炉に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a fast breeder reactor in which the reactor output can be normally controlled even when an earthquake occurs.

〔発明の技術的背景〕[Technical background of the invention]

従来、第1図に示すようなタンク形為速増殖炉が使用さ
れている.図中1は原子炉容器であシ、この原子炉容器
1内には冷却材である液体ナトリウム2が満たされてい
る.を九、この原子炉容器1内には炉心3が構成され、
かつ炉心上部機#I4、一次冷却材ポング5、中間熱交
換機6等が収容されている.そして、この原子炉容器1
の上部は上部遮蔽体としてのルーフスラブ7で密閉され
ておシ、このルーフスラブ1と液体ナトリウム2の液面
との間にはカバーガスが封入されている.そして、この
ルーフスラブ1の中央部には制御棒駆動機構8・・・が
支持されている。この制御棒駆動機構8はルーフスラブ
上の駆動部、ルーフスラブ下面側の上部案内管12、延
長管ISとで構成されている。そして、この制御棒駆動
機構8・・・は制御棒10・・・を炉心3に対して挿入
・引抜操作して、炉心3の反応度の制御を行なうもので
−ある。そして、制御棒10・・・はその機能によ船主
炉停止用制御棒と後備炉停止用制御棒とに分類され、主
炉停止用制御棒は通常運転時に炉心3に部分挿入され炉
心3の反応度を制御し、後備炉停止用制御棒はスクラム
時に炉心Jに全挿入されるものであるが、ここでは主炉
停止用制御棒についてのみ考察する仁ととする。
Conventionally, a tank-type rapid breeder reactor as shown in Figure 1 has been used. In the figure, 1 is a reactor vessel, and this reactor vessel 1 is filled with liquid sodium 2, which is a coolant. Nine, a reactor core 3 is configured within this reactor vessel 1,
It also houses the upper core machine #I4, primary coolant pump 5, intermediate heat exchanger 6, etc. And this reactor vessel 1
The upper part of the tank is sealed with a roof slab 7 as an upper shield, and a cover gas is sealed between the roof slab 1 and the liquid level of the liquid sodium 2. A control rod drive mechanism 8 is supported at the center of the roof slab 1. The control rod drive mechanism 8 includes a drive section on the roof slab, an upper guide tube 12 on the lower surface of the roof slab, and an extension tube IS. The control rod drive mechanism 8 controls the reactivity of the core 3 by inserting and withdrawing the control rods 10 into and out of the core 3. The control rods 10 are classified into main reactor shutdown control rods and backup reactor shutdown control rods according to their functions, and the main reactor shutdown control rods are partially inserted into the reactor core 3 during normal operation. The control rods for controlling the reactivity and for stopping the backup reactor are fully inserted into the reactor core J during scram, but here we will only discuss the control rods for stopping the main reactor.

第2図に示すように炉心3の中央部に配設された炉心燃
料9中には制御棒10・・・を挿通適せる下部案内管1
1・・・が設けられている。そして、上記制御棒駆動機
構8・・・は上記ルーフスラ、f1に支持された上部案
内管12・・・内にそれぞれ延長管IJ・・・を鉛直方
向に配設し、各延長管11方よ如上配下部案内管11内
に挿入さ・せ、ルーフスラブ上の駆動部によシ各延長管
を上下方向へ駆動することKようて、制御棒10・・・
を挿入あるいは引抜動作させるように構成されている。
As shown in FIG. 2, a lower guide tube 1 into which control rods 10 are inserted is inserted into the core fuel 9 disposed in the center of the reactor core 3.
1... is provided. The control rod drive mechanism 8... has extension tubes IJ vertically disposed within the upper guide tube 12 supported by the roof slider f1, and extends from each extension tube 11 side. The control rod 10...
The device is configured to be inserted or pulled out.

〔背景技術の間遍点〕[Intermediate point of background technology]

前記従来の高速増殖炉では次のような不具合があった。 The conventional fast breeder reactor had the following problems.

すなわち、高速増殖炉一般について言えることであるが
、特にタンク形高速増殖炉では原子炉容器1内に一次冷
却材Iンプ5、中間熱交換機6等を収容しているため原
子炉容器1が大形となりm然上部迩蔽体としてのルーフ
スラ!1も大径となる。したがつて、地震が発生した場
合には原子炉容器1の振幅・周期とルーフスラ!1の振
幅・周期との間に大きな差異が生じることになる。そこ
で、・第3図に示すようにルーフスラブ1が原子炉容器
1よ゛シ浮き上9、制御棒駆動機構8との上下方向の距
離が増大するようなことも予想される。このよう、な場
合、すべての制御棒10・・・は炉心3に対し引抜方向
へ移動することになり、炉心3には正の反応度が挿入さ
れ炉出力が急上昇することになゐ。
In other words, this is true for fast breeder reactors in general, but especially for tank-type fast breeder reactors, the reactor vessel 1 is large because the primary coolant Imp 5, intermediate heat exchanger 6, etc. are housed in the reactor vessel 1. The roof sura suddenly takes shape and acts as an upper covering body! 1 also has a large diameter. Therefore, in the event of an earthquake, the amplitude and period of the reactor vessel 1 and the roof slide! There will be a large difference between the amplitude and period of 1. Therefore, as shown in FIG. 3, it is expected that the roof slab 1 will float 9 higher than the reactor vessel 1 and the distance in the vertical direction from the control rod drive mechanism 8 will increase. In such a case, all the control rods 10 will move in the withdrawal direction with respect to the reactor core 3, and a positive reactivity will be inserted into the reactor core 3, causing a sudden increase in reactor power.

よって、制御棒10・・・によゐ炉出力の制御が正常に
行なわれなくなり、炉心3に苛酷な熱的負荷が加えられ
る事態が生じるおそれがありた。
Therefore, the control rods 10 may not be able to properly control the reactor output, and there is a risk that a severe thermal load will be applied to the reactor core 3.

〔発明の目的〕[Purpose of the invention]

本発明の目的は地震の振動等によって制御棒駆動機構と
炉心との相対的位置が変動しても正常に炉出力の制御が
行なわれる高速増殖炉を提供するととKある。
An object of the present invention is to provide a fast breeder reactor in which the reactor output can be normally controlled even if the relative position between the control rod drive mechanism and the reactor core changes due to earthquake vibrations or the like.

〔発明0IIEIE ) 本発明の高速増殖炉祉、前記制御棒駆動機構を炉心の下
部に設けられ九炉心支持板に支持させるようにし、制御
棒駆動機構と上部遮蔽体との間にベローズ機構を設けて
気密性を保持しかつ制御棒駆動機構と上部遮蔽体とを変
位自在にするようにしたものである。
[Invention 0IIEIE] In the fast breeder reactor system of the present invention, the control rod drive mechanism is provided at the lower part of the reactor core and supported by nine core support plates, and a bellows mechanism is provided between the control rod drive mechanism and the upper shield. The control rod drive mechanism and the upper shield are designed to maintain airtightness and to be freely displaceable.

〔発明の実施例〕[Embodiments of the invention]

本発明の実施例を第4図ないし第8図にし九がって説−
する、第4図社タンク形高速増殖炉の概の構成を示すも
ので、図中14は原子炉容器であって、この原子炉容器
14内には冷却材である液体ナトリウム16が満たされ
ている。
Embodiments of the present invention will be explained with reference to FIGS. 4 to 8.
Figure 4 shows the general configuration of a tank-type fast breeder reactor. In the figure, 14 is a reactor vessel, and this reactor vessel 14 is filled with liquid sodium 16, which is a coolant. There is.

また、この原子炉容1)J4内には炉心支持板16A上
に支持され九炉心16が構成され、かつ炉心上部機構1
1、−次冷却材ポンflll、中間熱交換機19等が収
容されている。そして、この原子炉容器14の上部は上
部遮蔽体としてのルーフスラブ20で密閉されておシ、
このルーフスラブ20と液体ナトリウムIIの液面との
間にはカバーガスが対人されている。上記ルーフスラブ
xoq)中央部には制御棒駆動機構U・・・が設けられ
、この制御棒駆動機構111−1炉心支持板ighK支
持されている。制御棒駆動機構21は第5図に示すよう
に、駆動部21と案内管23と延長管24および制御棒
2Jを保持するラッチ機構26とからなシ、制御棒25
を延長管24内で上下移動させ、また制御棒駆動機構1
ユを炉心16から抜き取るときにはラッチ機構を解動作
させ制御棒1sを〆、シ。
Further, within this reactor volume 1) J4, nine reactor cores 16 are configured supported on a core support plate 16A, and a core upper mechanism 1
1, a secondary coolant pump, an intermediate heat exchanger 19, etc. are accommodated. The upper part of this reactor vessel 14 is sealed with a roof slab 20 as an upper shield.
A cover gas is provided between the roof slab 20 and the liquid level of liquid sodium II. A control rod drive mechanism U... is provided in the center of the roof slab xoq), and this control rod drive mechanism 111-1 is supported by a core support plate ighK. As shown in FIG. 5, the control rod drive mechanism 21 includes a drive section 21, a guide tube 23, an extension tube 24, a latch mechanism 26 for holding the control rod 2J, and a control rod 25.
is moved up and down within the extension tube 24, and the control rod drive mechanism 1
When removing the unit from the core 16, the latch mechanism is released and the control rod 1s is closed and shut.

/ y ) l j B上に落下させるように構成され
ている。
/ y ) l j B.

上記案内管21は駆動部22の下面に固定され炉心燃料
22を貫通して、内部に嬌長管24゜制御棒25を収容
している。案内管23の中央部には透孔21・・・が設
けられておシ、内部に冷却材を流通させるように構成さ
れている。そして、案内管23の下端部内面には第6図
に示す着脱機構としての複数の係合爪28・・・が周方
向等間隔に固定されてお夛、案内管23を上記炉心支持
板JgAに着脱自在に支持している。上記係合爪sr゛
はたとえばインコネル等のバネ鋼で形成され、上記炉心
支持板16ムに設けられた係合溝28に係合し、着脱時
に祉案内管23全体を押込みあるいは引抜く外力によっ
て内径方向に収縮して着脱で舞るように構成されている
。を九、上記駆動部z2の外周聞とルーフスフ220と
の間にはベローズ機構29が設けられてお)、気密性を
保持するとともに上記制御棒駆動機構Lユとルーフスラ
ブ20とが相対的に変位できるように構成されている。
The guide tube 21 is fixed to the lower surface of the drive section 22, passes through the core fuel 22, and accommodates a 24° elongated tube control rod 25 therein. A through hole 21 is provided in the center of the guide tube 23, and the guide tube 23 is configured to allow a coolant to flow therein. On the inner surface of the lower end of the guide tube 23, a plurality of engaging claws 28 as an attachment/detachment mechanism shown in FIG. 6 are fixed at equal intervals in the circumferential direction. It is supported in a detachable manner. The engaging claw sr' is made of spring steel such as Inconel, and engages with the engaging groove 28 provided in the core support plate 16m, and is activated by an external force to push or pull out the entire service guide tube 23 during attachment/detachment. It is configured to contract in the inner diameter direction and float when attached and detached. (9) A bellows mechanism 29 is provided between the outer periphery of the drive section z2 and the roof slab 220) to maintain airtightness and to ensure that the control rod drive mechanism L and the roof slab 20 are relative to each other. It is configured to be movable.

上記構成のものは次のように作用効果を奏する。万一、
地震が発生した時にはルー7スラシ20および原子炉容
器14が激しく振動し、正常な状態を示すjI7図と比
較して第8図に示すようにルーフスラブ2oが原子炉容
器14がら浮き上ってルーフスラブ2oと炉心ICとの
上下方向の距離が増大することが予想される。このよう
な場合でも上記構成のものでは制御棒駆動機構υ・・・
は炉心支持板16ムに支持されているので制御棒2jと
炉心16との相対位置が変化せず炉出力の制御を正常に
行なうことができる。
The above configuration has the following effects. In the unlikely event that
When an earthquake occurs, the roof slab 20 and the reactor vessel 14 vibrate violently, and the roof slab 2o lifts up from the reactor vessel 14, as shown in Figure 8, compared to Figure 7, which shows a normal state. It is expected that the vertical distance between the roof slab 2o and the core IC will increase. Even in such a case, with the above configuration, the control rod drive mechanism υ...
Since the control rods 2j are supported by the core support plate 16m, the relative position between the control rods 2j and the reactor core 16 does not change, and the reactor output can be normally controlled.

また、上記制御棒駆動機構L」・・・Kは、2ツチ機構
26と係合爪21・・・が設けられているので、燃料交
換時にはう、チ機構26を解動作させ111j御棒25
を炉心J6内に落下させ、上記駆動部22と案内管23
を上方に引抜いて炉心燃料16を交換することができる
In addition, since the control rod drive mechanism L''...K is provided with a two-way mechanism 26 and an engaging pawl 21..., the second mechanism 26 is disengaged when changing fuel, and the 111j control rod 25 is disengaged.
is dropped into the reactor core J6, and the drive section 22 and guide tube 23 are
The core fuel 16 can be replaced by pulling it upward.

なお、本発明は以上の一実施例に限定されるもOではな
い、tず、本発明はタンク形高速増殖炉に限らずルー!
形の屯Oにも適用できる。
It should be noted that the present invention is not limited to the above-mentioned embodiment; however, the present invention is not limited to tank-type fast breeder reactors.
It can also be applied to the shape of tun O.

オた、上記係合爪21・・・は案内管210内局面に固
定されたものに限らず、外周面に固定してもよい。
Additionally, the engaging claws 21 are not limited to being fixed to the inner surface of the guide tube 210, but may be fixed to the outer peripheral surface.

〔発明の効果〕〔Effect of the invention〕

本発明による高速増殖炉は、炉心下部の炉心支持板で制
御棒駆動機構を支持するようKしたものである。したが
って、地震による振Wk等で上部遮蔽体と炉心との距離
が広がり九場合でも炉心に挿入される反応度は通常時と
変らず、正常な炉出力の制御を行なう仁とができる等そ
O効果拡大である。
The fast breeder reactor according to the present invention is designed so that a control rod drive mechanism is supported by a core support plate at the bottom of the reactor core. Therefore, even if the distance between the upper shield and the reactor core increases due to vibrations caused by an earthquake, etc., the reactivity of the reactor inserted into the reactor core remains the same as in normal times, making it possible to control the reactor output normally. This is an expansion of the effect.

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

第1図は従来のタンク形高速増殖炉を示す縦断面図、第
2図および第3図は従来の制御棒駆動機構を示す構成図
、銀4図は本発明の一実施例を示す縦断面図、第5il
Iは本発明の一1I麹例に會まれる制御棒駆動機構の縦
断面図、第6図は第smo*部断面図、第7図および第
5aiaa本発吻の−!J施例の構成図である。 14・・・原子炉容器、16・・・炉心、1σム・・・
炉心支持板、20・・・ルーフスラブ(上部遮蔽体)、
U・・・制御棒駆動機構、22・・・炉心燃料、21・
・・係止爪(着脱機構)、29・・・ベローズ機構。 出願人代理人  弁理士 鈴 江 武 彦第4図 ′lA5図 86図 第7図
Figure 1 is a vertical cross-sectional view showing a conventional tank-type fast breeder reactor, Figures 2 and 3 are configuration diagrams showing a conventional control rod drive mechanism, and Figure 4 is a vertical cross-sectional view showing an embodiment of the present invention. Fig. 5il
I is a vertical sectional view of the control rod drive mechanism that is used in the 11I koji example of the present invention, FIG. 6 is a sectional view of the smo* section, FIG. 7, and 5aiaa -! of the main proboscis. It is a block diagram of Example J. 14...Reactor vessel, 16...Reactor core, 1σm...
Core support plate, 20... roof slab (upper shield),
U... Control rod drive mechanism, 22... Core fuel, 21.
...Latching claw (attachment/detaching mechanism), 29...Bellows mechanism. Applicant's agent Patent attorney Takehiko Suzue Figure 4'lA5 Figure 86 Figure 7

Claims (1)

【特許請求の範囲】 (1)  原子炉容器内に設けられた炉心と、仁の炉心
の下端部に設けられ炉心を支持する炉心支持板と、上記
原子炉容器上方を閉塞する上部遮蔽体と、この上部遮蔽
体を貫通し上記炉心支持板に支持された制御棒駆動機構
と、この制御棒駆動機構の下部に設けられた着脱機構と
、上記制御棒駆動機構と上部遮蔽体とを変位自在かつ気
密に保持するベローズ機構とを具備した仁とを特徴とす
る高速増殖炉。 (2)  前記制御棒駆動機構は、上記炉心を上下に貫
通して設けられた円筒形め延長管を有し、この延長管の
下端部に前記着脱機構が設けられていることを特徴とす
る特許 (1)項記載の高速増殖炉。 (3)前記着脱機構は前記制御棒駆動機構の下端部に固
定されバネ鋼で形成された係合爪を前記炉心支持板に係
合させたものであるζとを特徴とする前記特許請求の範
囲第(1)項記載の高速増殖炉。
[Scope of Claims] (1) A reactor core provided in a reactor vessel, a core support plate provided at the lower end of the reactor core to support the core, and an upper shield that closes off the upper part of the reactor vessel. , a control rod drive mechanism that passes through the upper shield and is supported by the core support plate, an attachment/detachment mechanism provided at the bottom of the control rod drive mechanism, and the control rod drive mechanism and the upper shield are freely displaceable. A fast breeder reactor characterized by a bellows mechanism that maintains airtightness. (2) The control rod drive mechanism has a cylindrical extension tube provided vertically penetrating the reactor core, and the attachment/detachment mechanism is provided at the lower end of the extension tube. Fast breeder reactor described in patent (1). (3) The attachment/detachment mechanism is fixed to the lower end of the control rod drive mechanism and has an engaging pawl formed of spring steel that engages with the core support plate. A fast breeder reactor according to scope item (1).
JP57044182A 1982-03-19 1982-03-19 Fast breeder reactor Pending JPS58161882A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57044182A JPS58161882A (en) 1982-03-19 1982-03-19 Fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57044182A JPS58161882A (en) 1982-03-19 1982-03-19 Fast breeder reactor

Publications (1)

Publication Number Publication Date
JPS58161882A true JPS58161882A (en) 1983-09-26

Family

ID=12684427

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57044182A Pending JPS58161882A (en) 1982-03-19 1982-03-19 Fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS58161882A (en)

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