JPS63246699A - Support structure of nuclear-reactor in-core structure - Google Patents

Support structure of nuclear-reactor in-core structure

Info

Publication number
JPS63246699A
JPS63246699A JP62077464A JP7746487A JPS63246699A JP S63246699 A JPS63246699 A JP S63246699A JP 62077464 A JP62077464 A JP 62077464A JP 7746487 A JP7746487 A JP 7746487A JP S63246699 A JPS63246699 A JP S63246699A
Authority
JP
Japan
Prior art keywords
reactor
core
nuclear
coolant
internals
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
JP62077464A
Other languages
Japanese (ja)
Inventor
博文 近藤
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 JP62077464A priority Critical patent/JPS63246699A/en
Publication of JPS63246699A publication Critical patent/JPS63246699A/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

  • Housings And Mounting Of Transformers (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】 〔発明の目的〕 (産業上の利用分野) 本発明は、冷却材として液体金属を用いるとともに、炉
内構造物が原子炉容器内の上記冷却材中に吊下げ支持さ
れた原子炉における原子炉炉内構造物の支持構造に関す
る。
Detailed Description of the Invention [Objective of the Invention] (Industrial Field of Application) The present invention uses a liquid metal as a coolant, and a structure in which reactor internals are suspended and supported in the coolant in a reactor vessel. The present invention relates to a support structure for internal reactor structures in a nuclear reactor.

(従来の技術) 原子炉、たとえば高速増殖炉は、一般に、冷却材として
液体金属ナトリウムで代表される液体金属を用い、かつ
軽水炉型原子炉に比較して高い温度で運転される。この
ような高速増殖炉にあっては、〃バ子炉運転開始時や停
止時に原子炉主容器。
(Prior Art) Nuclear reactors, such as fast breeder reactors, generally use liquid metal, typified by liquid metal sodium, as a coolant, and are operated at higher temperatures than light water reactors. In such a fast breeder reactor, the reactor main vessel is used at the time of starting or stopping the reactor operation.

炉心機材、配管等が熱応力で損傷されるのを防止するた
め、通常、これらの構成部材の肉厚を薄くする方式が採
用されている。
In order to prevent core equipment, piping, etc. from being damaged by thermal stress, a method is usually adopted to reduce the thickness of these structural members.

また、このような高速増殖炉全体を簡潔な構造とする為
に、可能な限り配管類を無くすようにした原子炉、すな
わち、具体的には一次冷却材と二次冷却材とを熱交換さ
せる中間熱交換器や冷却材循環ポンプを原子炉主容器内
に設「Cするようにした、いわゆるタンク型原子炉梼造
が考えられている。このタンク型原子炉は、たとえば第
3図に示すように、JM子炉主容器1の図中上方開口部
をルーフスラブ2で閉塞し、内部に炉心3.炉心上部機
構4.中間熱交換器5.冷却材循環ポンプ6および冷却
材7を収容して構成されている。炉心3はルーフスラブ
2から吊下げられた炉心支持部材8の図中下端部に収容
されており、炉心上部機構4は、上記炉心支持部材8の
上方に回転自在に設けられた回転プラグ9に支持されて
いる。なお、原子炉主容器りは、リングガータlOを介
して原子炉室11に吊下げられており、原子炉主容器1
の外側にはこの原子炉主容器1を覆うように安全容器1
2が設けられている。
In addition, in order to make the overall structure of such a fast breeder reactor simple, a nuclear reactor that eliminates piping as much as possible, that is, a reactor that exchanges heat between the primary coolant and the secondary coolant. A so-called tank-type reactor structure is being considered, in which an intermediate heat exchanger and a coolant circulation pump are installed inside the main reactor vessel. The upper opening in the figure of the JM child reactor main vessel 1 is closed with a roof slab 2, and the reactor core 3, core upper mechanism 4, intermediate heat exchanger 5, coolant circulation pump 6, and coolant 7 are housed inside. The core 3 is housed at the lower end in the figure of a core support member 8 suspended from the roof slab 2, and the core upper mechanism 4 is rotatably mounted above the core support member 8. The reactor main vessel is supported by a rotary plug 9 provided therein.The reactor main vessel is suspended in the reactor chamber 11 via a ring garter lO, and the reactor main vessel
There is a safety vessel 1 on the outside of the reactor so as to cover this reactor main vessel 1.
2 is provided.

このようなタンク型原子炉構造を採用することによって
、−次熱交換系一冷却材循環系の配管を削除することが
できる。
By adopting such a tank-type nuclear reactor structure, piping for the secondary heat exchange system and coolant circulation system can be eliminated.

(発明が解決しようとする問題点) しかしながら、このようなタンク型原子炉構造を採用し
た原子炉であっても次のようなことが予想される。すな
わち、炉心支持部材8.中間熱交換器5および循環ポン
プ6等は熱応力上の面から比較的薄肉に形成され、かつ
大型化に判なう大きな熱膨張量を吸収するために、ルー
フスラブ2に支持されて原子炉主容器1内に吊下げられ
た片持梁構造となっている。したがって、外部からの衝
撃入力または振動入力が加わった場合、それらに大きな
振動が発生し、その変形による局部的応力の増大で一部
が損傷を受ける可能性があり何らかの対策が望まれる。
(Problems to be Solved by the Invention) However, even in a nuclear reactor that employs such a tank-type reactor structure, the following problems are expected. That is, the core support member 8. The intermediate heat exchanger 5, circulation pump 6, etc. are formed with relatively thin walls in view of thermal stress, and are supported by the roof slab 2 to absorb the large amount of thermal expansion that occurs when the reactor is enlarged. It has a cantilever structure suspended within the main container 1. Therefore, when an external impact input or vibration input is applied, large vibrations are generated in them, and a portion may be damaged due to an increase in local stress due to the deformation, so some countermeasure is desired.

本発明は上述の事情に鑑みてなされたもので、その目的
とするところは、熱膨張のようなゆっくりとした変形に
対しては何ら拘束を与えず、地震発生時等における炉内
構造物の水平方向の揺れを確実に抑制することができ、
地震時等における炉全体の健全性の向上を図ることがで
きる原子炉炉内構造物の支持構造を提供することにある
The present invention was made in view of the above-mentioned circumstances, and its purpose is to provide no restraints to slow deformation such as thermal expansion, and to improve the structure of reactor internals during earthquakes. Horizontal shaking can be reliably suppressed,
An object of the present invention is to provide a support structure for internal structures of a nuclear reactor, which can improve the health of the entire reactor during an earthquake or the like.

〔発明の構成〕[Structure of the invention]

(問題点を解決するための手段) 本発明は冷却材として液体金属を用いるとともに炉心中
間熱交換器あるいは循環ポンプ等の炉内構造物が原子炉
容器内の冷却材中に吊下げ支持された原子炉において、
炉内構造物の側面を流体ギャップを介して覆うように設
けられた筒状部材と、この筒状部材を原子炉器に固定す
る部材と、炉内構造外周または筒状部材内周のいずれか
一方に設けられた溝内に収容された環状部材とを有し、
環状部材か、あるいはそれに対接する筒状部材の表面ま
たは炉内構造物の表面か、いずれか一方に突出部が形成
されていることを特徴としている。
(Means for Solving the Problems) The present invention uses liquid metal as a coolant, and the reactor internals such as the core intermediate heat exchanger or the circulation pump are suspended and supported in the coolant in the reactor vessel. In a nuclear reactor,
A cylindrical member provided to cover the side surface of the reactor internal structure through a fluid gap, a member that fixes this cylindrical member to the reactor vessel, and either the outer periphery of the reactor internal structure or the inner periphery of the cylindrical member. an annular member housed in a groove provided on one side;
It is characterized in that a protrusion is formed on either the annular member, the surface of the cylindrical member in contact with the annular member, or the surface of the furnace internal structure.

(作 用) 地震時において、炉内構造物が原子炉主容器に対して相
対移動を起した場合には1M子炉主容器に固定された筒
状部材と上記炉内構造物との間に相対変位が生じ、流体
ギャップに大きな圧力差が生じ、この圧力差が炉内構造
物の相対運動に対して低抗力として作用する。
(Function) During an earthquake, if the reactor internals move relative to the reactor main vessel, there will be a gap between the cylindrical member fixed to the 1M sub-reactor main vessel and the reactor internals. Relative displacement occurs, creating a large pressure difference in the fluid gap, which acts as a low drag on the relative movement of the reactor internals.

ところで、一般に物体が周囲の流体から受ける抵抗力に
は、物体の加速度に比例する力と物体の速度(あるいは
速度の2乗)に比例する力とが含まれている。加速度に
比例する力は流体ギャップからの上下方向への流体のも
れが小さいほど大きくなるが、速度に比例する力は上下
方向へのもれがある程度小さくなったところで非常に大
きくなり、それよりももれが小さくなると逆に小さくな
ってしまうという性質を有している。
Incidentally, the resistance force that an object receives from the surrounding fluid generally includes a force proportional to the acceleration of the object and a force proportional to the speed (or the square of the speed) of the object. The force proportional to acceleration becomes larger as the leakage of fluid in the vertical direction from the fluid gap becomes smaller, but the force proportional to velocity becomes extremely large when the leakage in the vertical direction becomes small to a certain extent, and then It has the property that when the leakage becomes smaller, the leakage becomes smaller.

本発明では環状部材によって流体のもれを防いでいるが
、環状部材か、あるいは、それに対接する筒状部材の表
面または炉内構造物の表面か、いずれか一方に突出部を
設けることによりそれらが完全に密着することを防いで
いるので、炉内構造物の振動に対する抵抗力を最大にコ
ントロールすることができる。従って、本発明による原
子炉炉内構造物の支持構造によれば熱応力を発生させず
に、炉内構造物の振動を効率的に抑制することができる
In the present invention, the annular member prevents fluid leakage, but this can be prevented by providing a protrusion on either the annular member, the surface of the cylindrical member that is in contact with it, or the surface of the reactor internal structure. Since this prevents the parts from coming into close contact with each other, the resistance to vibration of the reactor internals can be controlled to the maximum. Therefore, according to the support structure for nuclear reactor internals according to the present invention, vibrations of the reactor internals can be efficiently suppressed without generating thermal stress.

(実施例) 以下、第1図および第2図を参照し、本発明の一実施例
について説明する・ 第1図は本発明による炉内構造物の支持構造を採用した
タンク型原子炉の縦断面を示した図である。炉心支持材
8の周囲に冷却材の満たされた流体ギャップ13を介し
て円筒部材14が支持板15によって主容器1に固定さ
れている。円筒部材の上下端近傍の内周にはL形の溝が
切欠かれており、この中に断面矩形のリング16が収容
されている。
(Embodiment) An embodiment of the present invention will be described below with reference to FIGS. 1 and 2. FIG. FIG. A cylindrical member 14 is fixed to the main vessel 1 by a support plate 15 via a fluid gap 13 filled with coolant around the core support member 8 . An L-shaped groove is cut in the inner periphery near the upper and lower ends of the cylindrical member, and a ring 16 having a rectangular cross section is accommodated in this groove.

第2図は、リング16およびその近傍の拡大断面図であ
る。上記のリングには上面、下面および内周面には微小
高さの突出部17が配列されており、これによってリン
グと炉内構造物、リング16と円筒部材溝内面との間に
挟い流通器18が形成されている。
FIG. 2 is an enlarged sectional view of the ring 16 and its vicinity. The above-mentioned ring has protrusions 17 of very small height arranged on the upper surface, lower surface, and inner circumferential surface of the ring. A container 18 is formed.

本支持構造によれば、流体ギャップからの流体のもれを
最適な量にコントロールでき、熱応力を発生させないで
炉内構造物の振動を最大限に抑制させることができる。
According to this support structure, leakage of fluid from the fluid gap can be controlled to an optimum amount, and vibration of the reactor internal structure can be suppressed to the maximum without generating thermal stress.

〔発明の効果〕〔Effect of the invention〕

本発明の炉内構造物の支持構造によれば、流体ギャップ
からの流体のもれを退散にすることによって支持効果を
非常に大きくすることができ、しかも機械的支持にみら
れるような熱応力の発生はない。
According to the support structure of the reactor internal structure of the present invention, the support effect can be greatly increased by dissipating fluid leakage from the fluid gap, and the thermal stress seen in mechanical support can be greatly increased. There has been no occurrence of

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

第1図は本発明による炉内構造物の支持構造を採用した
原子炉の断面図、第2図は第1図のリングとその近傍を
示した拡大断+f+r図、第3図は従来の原子炉の断面
図である。 1・・・原子炉主容器    12・・・安全容器2・
・・ルーフスラブ    13・・・流体ギャップ3・
・・炉心        14・・・円筒部材4・・・
炉心上部機構    15・・・支持板5・・・中間熱
交換器    16・・・リンク6・・・循環ポンプ 
    17・・・突出部7・・・冷却材      
 18・・・微小流通路8・・・炉心 9・・・炉心支持部材 10・・・リングガータ 11・・・原子炉室 代理人 弁理士 則 近 憲 佑 も、−
Figure 1 is a cross-sectional view of a nuclear reactor that employs the support structure for reactor internals according to the present invention, Figure 2 is an enlarged cross-sectional +f+r diagram showing the ring and its vicinity in Figure 1, and Figure 3 is a conventional atomic reactor. FIG. 3 is a cross-sectional view of the furnace. 1... Reactor main vessel 12... Safety vessel 2.
...Roof slab 13...Fluid gap 3.
...Core 14...Cylindrical member 4...
Core upper mechanism 15...Support plate 5...Intermediate heat exchanger 16...Link 6...Circulation pump
17...Protrusion part 7...Cooling material
18...Minute flow passage 8...Core 9...Core support member 10...Ring gutter 11...Reactor room representative Patent attorney Noriyuki Chika, -

Claims (1)

【特許請求の範囲】[Claims] 冷却材として液体金属を用いるとともに炉心、中間熱交
換器、循環ポンプの炉内構造物が原子炉容器内の上記冷
却材中に吊下げ支持された原子炉において、上記炉内構
造物の側面と流体ギャップを介して対向するようにその
側面が設けられた筒状部材と、この筒状部材を前記原子
炉容器に固定する部材と、前記側面の一方に設けられた
溝内に収容された環状部材を有し、前記他方の側面に、
前記溝に係合する突出部が形成されていることを特徴と
する原子炉炉内構造物の支持構造。
In a nuclear reactor in which a liquid metal is used as a coolant and reactor internals such as a core, an intermediate heat exchanger, and a circulation pump are suspended and supported in the coolant in the reactor vessel, the side surfaces of the reactor internals and A cylindrical member whose side surfaces are arranged to face each other across a fluid gap, a member for fixing the cylindrical member to the reactor vessel, and an annular member housed in a groove provided in one of the side surfaces. a member, on the other side;
A support structure for a nuclear reactor internal structure, characterized in that a protrusion that engages with the groove is formed.
JP62077464A 1987-04-01 1987-04-01 Support structure of nuclear-reactor in-core structure Pending JPS63246699A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62077464A JPS63246699A (en) 1987-04-01 1987-04-01 Support structure of nuclear-reactor in-core structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62077464A JPS63246699A (en) 1987-04-01 1987-04-01 Support structure of nuclear-reactor in-core structure

Publications (1)

Publication Number Publication Date
JPS63246699A true JPS63246699A (en) 1988-10-13

Family

ID=13634718

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62077464A Pending JPS63246699A (en) 1987-04-01 1987-04-01 Support structure of nuclear-reactor in-core structure

Country Status (1)

Country Link
JP (1) JPS63246699A (en)

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