JPS59112283A - Reactor container structure - Google Patents

Reactor container structure

Info

Publication number
JPS59112283A
JPS59112283A JP57221832A JP22183282A JPS59112283A JP S59112283 A JPS59112283 A JP S59112283A JP 57221832 A JP57221832 A JP 57221832A JP 22183282 A JP22183282 A JP 22183282A JP S59112283 A JPS59112283 A JP S59112283A
Authority
JP
Japan
Prior art keywords
reactor
core
roof slab
reactor vessel
pump
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
JP57221832A
Other languages
Japanese (ja)
Inventor
寛 宮田
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP57221832A priority Critical patent/JPS59112283A/en
Publication of JPS59112283A publication Critical patent/JPS59112283A/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

  • Structure Of Emergency Protection For Nuclear Reactors (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】 本発明はタンク型FB凡の炉容器構造に係り、特に全体
構造の軽量化を計り、且つ耐震性に好適な原子炉の炉容
器構造に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a reactor vessel structure for a tank-type FB, and more particularly to a reactor vessel structure for a nuclear reactor that reduces the weight of the entire structure and is suitable for earthquake resistance.

FBRの従来例を第1図及び第2図において説明する。A conventional example of FBR will be explained with reference to FIGS. 1 and 2.

原子炉の熱源としての炉容器に固定された炉心1、炉心
において高温に加熱された一次流体2と炉容器3の外部
に導かれる二次流体間の熱交換を行う中間熱交換器4、
炉容器内の低温−次流体5を炉心に循環させるポンプ6
、及びこれらを内蔵する炉容器3は炉容器3の蓋である
ルーフ・スラブ7によって吊持ちされている。一方、中
性子吸収材を内蔵を制@1棒(図示せず)は炉心1に挿
入され原子炉反応を制御しているが、この制御棒はルー
フ・スラブ7に設置された制御棒駆動装置(図示せず)
より吊下げられている、さて、原子炉を運転中の炉心1
の反応度制御は制御棒の炉心1への挿入度を調整するこ
とにより行われる。通常の運転状態では制御棒の上下の
必要制御は比較的緩やかであシ、制御棒駆動装置により
容易に可能である。しかし、地震時等には、重量物であ
る中間熱交換器4、ポンプ6等を吊持ちし、且つその直
径は20mにも及ぶルーフ・スラブ7は高周波数で上下
動し、その変位量は犬きく 、fij’J御棒駆動追従
性が不十分であると反応は不安定となり、制御棒が炉心
1により多く挿入されると反応度は制御されるが、逆の
場合には反応が促進される結果、極端な場合には即発臨
界の状態となり得る欠点があった。また、水平動地震に
対処するた応堅固で且つ炉容器全体の熱膨張量を吸収可
能な支持構造の設計が極めて困難であるという欠点があ
った。
A reactor core 1 fixed to a reactor vessel as a heat source of the reactor; an intermediate heat exchanger 4 that exchanges heat between a primary fluid 2 heated to a high temperature in the reactor core and a secondary fluid led to the outside of the reactor vessel 3;
A pump 6 that circulates the low-temperature fluid 5 in the reactor vessel to the reactor core.
, and the furnace vessel 3 containing these are suspended by a roof slab 7 that is the lid of the furnace vessel 3. On the other hand, a control rod (not shown) containing a built-in neutron absorber is inserted into the reactor core 1 and controls the reactor reaction. (not shown)
Now, the core 1 of the nuclear reactor in operation is suspended from the ground.
The reactivity control is performed by adjusting the degree of insertion of the control rods into the reactor core 1. Under normal operating conditions, the necessary vertical control of the control rods is relatively gradual and is easily achieved by the control rod drive. However, during an earthquake, the roof slab 7, which suspends the heavy intermediate heat exchanger 4, pump 6, etc. and has a diameter of 20 m, moves up and down at high frequency, and the amount of displacement is small. If the control rod drive followability is insufficient, the reaction will become unstable, and if more control rods are inserted into the reactor core 1, the reactivity will be controlled, but in the opposite case, the reaction will be accelerated. As a result, in extreme cases, there was a drawback that a rapid criticality state could occur. Another disadvantage is that it is extremely difficult to design a support structure that is strong enough to withstand horizontal motion earthquakes and can absorb the amount of thermal expansion of the entire reactor vessel.

本発明の目的は原子炉寿命中一度起こるかどうかの極め
て大きな地震動に対しても、炉心の制御を安定に行え且
つ耐震上堅固な炉容器構造を提供することにある。
An object of the present invention is to provide a reactor vessel structure that is earthquake resistant and capable of stably controlling the reactor core even against extremely large seismic motions that may occur once during the life of the reactor.

本発明は直径20mにも及ぶルーフ・スラブの変形を考
え得る大きな地震時においても小さく抑えることによっ
て制御棒の上下動を許容値内にすることを目的として、
ルーフ・スラブをその外周部のみでなく、その内部にお
いても基礎より支持しようとするものである。また、−
次流体を官め大重量物である炉容器全体はルーフ・スラ
ブより吊持ちされているが、この炉容器全体の地震時の
水平動を抑制し、同時に炉容器全体の径方向熱変形量を
吸収し得る構造として、十字型の構造とすることによっ
て、水平動に関してはその直角方向の面で支持し得る構
造を提供することにある。
The purpose of the present invention is to keep the vertical movement of control rods within permissible limits by suppressing the deformation of roof slabs as large as 20 m in diameter even in the event of a large earthquake.
The idea is to support the roof slab from the foundation not only on its outer periphery but also on its interior. Also, -
The entire reactor vessel, which is a heavy object that regulates the flow of fluid, is suspended from the roof slab, which suppresses the horizontal movement of the entire reactor vessel during an earthquake, and at the same time reduces the amount of radial thermal deformation of the entire reactor vessel. By using a cross-shaped structure as an absorbable structure, the object is to provide a structure that can support horizontal movement in its perpendicular plane.

以下、本発明の一実施例を第3図及び第4図において説
明する。炉容器に固定された炉心11、中間熱交換器1
4、ポンプ16、及びこれらを内蔵する炉容器13はル
ーフ・スラブ17によって吊持ちされている。一方、制
御棒(図示せず)はルーフ・スラブ17に設置式れた制
御棒駆動装置(図示せず)より吊下げられ、炉心11に
挿入されている。炉容器13は断面十字形となっており
、それに合せて基礎18が4ケ所で構造中心方向に突出
している。ポンプ16は当該突出部に設けられた竪穴1
9内に配置され、且つ上記竪穴19には横穴20が設け
られた構造となっている。一方、ルーフ・スラブ17は
基礎184.’J突出部においても支持し得る構造とな
っている。
An embodiment of the present invention will be described below with reference to FIGS. 3 and 4. Core 11 fixed to the reactor vessel, intermediate heat exchanger 1
4, the pump 16, and the furnace vessel 13 containing them are suspended by a roof slab 17. On the other hand, control rods (not shown) are suspended from a control rod drive device (not shown) installed on the roof slab 17 and inserted into the reactor core 11. The furnace vessel 13 has a cruciform cross section, and four foundations 18 protrude toward the center of the structure. The pump 16 has a vertical hole 1 provided in the protrusion.
9 and has a structure in which a horizontal hole 20 is provided in the vertical hole 19. On the other hand, the roof slab 17 is attached to the foundation 184. 'It has a structure that can be supported even at the J protrusion.

いま、上下地震動が作用するとルーフ・スラブ17は上
下動することになるが、外径が約20mに及ぶにも拘ら
ず基礎18の突出部により中央部で支持されているため
、その変形量を小さく抑えることが出来るので、許容値
内に抑えることは極めて容易である。したがって即発臨
界の如き不安定な炉心制御に到らない。一方、水平地震
動に対しては基礎18の突出部を利用して床持出米るの
で、割振は極めて容易となる。
Now, when vertical earthquake motion acts, the roof slab 17 will move up and down, but since it is supported at the center by the protrusion of the foundation 18 even though its outer diameter is about 20 m, the amount of deformation can be reduced. Since it can be kept small, it is extremely easy to keep it within the allowable value. Therefore, unstable core control such as prompt criticality is not achieved. On the other hand, in response to horizontal earthquake motion, the protrusion of the foundation 18 is used to lift the floor, making allocation extremely easy.

さ−C1原子炉の機能としての熱流動は、基本的には従
来例(第1図)と違いはないが、中+fjl熱交換器に
て熱交換後の熱流体は基礎に設けられた横穴20(l−
通ってポンプに吸込まれる点が犬さな相違点である。な
おポンプは直接基詭18よシ吊下げることも可能で、ル
ーフ・スラブの設計は極めて容易になり、軽量化が計れ
ることになる。
The heat flow as a function of the S-C1 nuclear reactor is basically the same as that of the conventional example (Figure 1), but the heat fluid after heat exchange in the medium+fjl heat exchanger flows through a horizontal hole provided in the foundation. 20(l-
The difference is that it passes through the tube and is sucked into the pump. The pump can also be suspended directly from the base 18, which greatly simplifies the design of the roof slab and reduces its weight.

本発明によれは、ルーフ・スラブの基礎からの支持金ル
ーフ・スラブの外周部の会でなく、中央部においても可
1]目であるので、地震時のルーフ・スラブの変形を極
めて小さく仰えることが川口しであるので、吊−[げら
れた制御棒の上下動も小さく抑えられるので、即発臨界
など炉心反応度の不安定な変化に伴う核暴走を抑止出来
る。また、ルーフ・スラブに対する支付部が広範囲に存
在することになるので、ルーフ・スラブ自体の剛性を大
幅に低減しても必要な性能9機能を確保出来ると考えら
れる。
According to the present invention, the support metal from the foundation of the roof slab can be placed not only at the outer periphery of the roof slab but also at the center, so that the deformation of the roof slab during an earthquake can be minimized. Since the control rods are controlled by Kawaguchi, the vertical movement of the suspended control rods can be kept to a minimum, thereby preventing nuclear runaway caused by unstable changes in core reactivity, such as prompt criticality. Furthermore, since the supporting portions for the roof slab are spread over a wide area, it is thought that the necessary nine performance functions can be ensured even if the rigidity of the roof slab itself is significantly reduced.

また、水平地震に対しても動きに対し直角方向の基礎の
突出部が壁の役目を果たし有効な耐震構造となっている
In addition, the protrusion of the foundation in the direction perpendicular to the movement acts as a wall against horizontal earthquakes, making it an effective seismic structure.

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

第1図は従来例の正面図で概念的に示した正面図、第2
図は平面図、第3図は本発明の一実施例の正面図、第4
図は第3図に対応した平面図である。 11・・・炉心、13・・・炉容器、17・・・ルーフ
・スラブ、18・・・基礎、19・・・竪穴、20・・
・横穴。 ゝ゛4否、′、ゝ 芽1 目 茅2 口 第3 図 第4図 3
Figure 1 is a conceptual front view of a conventional example;
The figure is a plan view, the third figure is a front view of one embodiment of the present invention, and the fourth figure is a front view of an embodiment of the present invention.
The figure is a plan view corresponding to FIG. 3. 11... Reactor core, 13... Reactor vessel, 17... Roof slab, 18... Foundation, 19... Pit, 20...
・Horizontal hole. Figure 4 Figure 3

Claims (1)

【特許請求の範囲】[Claims] ■、炉心及び炉心を固定する炉心支持構造、さらに熱流
体を炉心を通して循環させるポンプ及び熱流体間の熱交
換乞行う中間熱交換器等を内蔵する炉容器と、炉心に挿
入される制御棒の駆動装置、上記ポンプ及び中間熱交換
器を載荷し、且つ炉容器全体を吊持ちするルーフ・スラ
ブよシなる原子炉において、ルーフ・スラブ外周のみな
らず、中央部にもルーフ・スラブ支持用支柱を用いるこ
とを特徴とする原子炉の炉容器構造。
■A reactor vessel containing a reactor core and a core support structure that fixes the core, a pump that circulates thermal fluid through the core, an intermediate heat exchanger that performs heat exchange between the thermal fluids, and a control rod that is inserted into the reactor core. In a nuclear reactor consisting of a roof slab that carries the driving device, the above-mentioned pump, and the intermediate heat exchanger, and suspends the entire reactor vessel, pillars for supporting the roof slab are installed not only around the outer periphery of the roof slab but also at its center. A reactor vessel structure for a nuclear reactor characterized by using.
JP57221832A 1982-12-20 1982-12-20 Reactor container structure Pending JPS59112283A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57221832A JPS59112283A (en) 1982-12-20 1982-12-20 Reactor container structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57221832A JPS59112283A (en) 1982-12-20 1982-12-20 Reactor container structure

Publications (1)

Publication Number Publication Date
JPS59112283A true JPS59112283A (en) 1984-06-28

Family

ID=16772886

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57221832A Pending JPS59112283A (en) 1982-12-20 1982-12-20 Reactor container structure

Country Status (1)

Country Link
JP (1) JPS59112283A (en)

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