JPS5845595A - Reactor - Google Patents

Reactor

Info

Publication number
JPS5845595A
JPS5845595A JP56143785A JP14378581A JPS5845595A JP S5845595 A JPS5845595 A JP S5845595A JP 56143785 A JP56143785 A JP 56143785A JP 14378581 A JP14378581 A JP 14378581A JP S5845595 A JPS5845595 A JP S5845595A
Authority
JP
Japan
Prior art keywords
reactor
vessel
shield plug
plug
nuclear 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
JP56143785A
Other languages
Japanese (ja)
Inventor
曾佐 豊
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
Tokyo Shibaura Electric 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP56143785A priority Critical patent/JPS5845595A/en
Publication of JPS5845595A publication Critical patent/JPS5845595A/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

  • Treatment Of Water By Oxidation Or Reduction (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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 本発明は液体金属冷却型原子炉に係り、時に炉容器と値
蔽プラグ間の環状間隙部に発生する自然対流に起因する
熱応力及び熱変形を緩和する機構を備えた原子炉に関す
る。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a liquid metal cooled nuclear reactor, and includes a mechanism for alleviating thermal stress and thermal deformation caused by natural convection that sometimes occurs in an annular gap between a reactor vessel and a shielding plug. Regarding nuclear reactors.

液体金属冷却型原子炉の炉容器は、その内部に炉心およ
び炉心の冷却を行う一次冷却材を有しているため、その
健全性に関して高い信頼性が要求される。しかるに、液
体金属冷却原子炉においては炉心出口の冷却材温度が高
く、したがって炉心出口冷却材に接する炉容器胴の温度
が高温となり炉容器の設計は厳しい高温構造設計条件が
要求され、非常に難しいものとなっている。一方原子炉
は、原子炉容器の上方開口端を閉塞して塔載されるじゃ
へいプラグと、前述炉容器胴との間には環状の間隙部が
構成されている。この間隙部には自然対流が発生し、炉
容器周方向に不均一な温度分布が生じる結果、熱応力や
炉容器の変形が発生する原因となる。
The reactor vessel of a liquid metal cooled nuclear reactor has a reactor core and a primary coolant for cooling the reactor core therein, and therefore requires high reliability regarding its soundness. However, in liquid metal cooled reactors, the temperature of the coolant at the core exit is high, and therefore the temperature of the reactor vessel shell in contact with the core outlet coolant is high, making the design of the reactor vessel extremely difficult as it requires strict high-temperature structural design conditions. It has become a thing. On the other hand, in a nuclear reactor, an annular gap is formed between the reactor vessel shell and a blocking plug mounted on the tower to close the upper open end of the reactor vessel. Natural convection occurs in this gap, resulting in non-uniform temperature distribution in the circumferential direction of the furnace vessel, which causes thermal stress and deformation of the furnace vessel.

この対策として、環状間隙下端をじゃま榎で塞ぐ等の対
策が取られている。自然対流を十分に抑制するためには
1間隙な糧めて狭くする必要があるが、製缶構造物の炉
容器及びしやへいプラグの寸法精度の問題、また炉容器
とじゃへいプラグの熱膨張差等から十分な効果を得るこ
とが困難であつた。さらに、原子炉の大型化に伴い、環
状間隙の高さが高くなると下端部のみを閉塞しても自然
対流を十分に抑制できないという問題が生じた。
As a countermeasure against this problem, measures such as closing the lower end of the annular gap with a jama-no-kana are taken. In order to sufficiently suppress natural convection, it is necessary to make each gap extremely narrow, but there are problems with the dimensional accuracy of the furnace vessel and the shield plug in the can-making structure, as well as the heat of the furnace vessel and the shield plug. It has been difficult to obtain sufficient effects due to differences in expansion and the like. Furthermore, as the size of nuclear reactors increases, the height of the annular gap increases, resulting in the problem that natural convection cannot be sufficiently suppressed even if only the lower end is closed.

本発明は以上の事情に対してなされたもので、その目的
とするところは、炉容器とじゃへいプラグとの間の環状
間隙部の自然対流を抑制し、不均一なmrti分布がな
く熱変形及び熱応力の小さい安全性の高い原子炉を提供
することにある。
The present invention has been made in view of the above-mentioned circumstances, and its purpose is to suppress natural convection in the annular gap between the furnace vessel and the Jahei plug, prevent uneven mrti distribution, and prevent thermal deformation. and to provide a highly safe nuclear reactor with low thermal stress.

以下本発明の一実施例を図面を参照しながら説明する。An embodiment of the present invention will be described below with reference to the drawings.

第1図は、本発明の原子炉の縦断面図であり、第2図は
第1図の対流防止ベローズ部の拡大断面図であるう 炉容器1は炉心2をその内部に収納しており、支持構造
物3によって支持されている。この炉容1%1の上部開
口部はしやへいプラグ4によって閉塞されており、この
しやへいプラグ4は支持構造物3の上部に設置された支
持スベー+Sによって支持されている。炉容a1の胴部
には内側へつば状に延長された炉心支持構造物6が設け
られ、炉心2を内包する。また炉容器1の底部には入口
ノズル7が設けられ、胴側部には出口ノズル8が設けら
れている。冷却材液面9と前記しゃへいプラグ4との間
にはカバーガス空間10が形成されている。炉容器1と
しやへいプラグ4との間には環状間隙部11が形成され
る。この環状間隙部11の高さ方向には複数個、下記の
対流防止べa−ズ20が取付けられる。
FIG. 1 is a longitudinal sectional view of the nuclear reactor of the present invention, and FIG. 2 is an enlarged sectional view of the convection prevention bellows part of FIG. 1.A reactor vessel 1 houses a reactor core 2 therein. , supported by the support structure 3. The upper opening of this furnace volume 1%1 is closed by a shield plug 4, and this shield plug 4 is supported by a support base +S installed on the upper part of the support structure 3. A core support structure 6 extending inward in the shape of a collar is provided in the body of the reactor volume a1, and encloses the core 2 therein. Further, an inlet nozzle 7 is provided at the bottom of the furnace vessel 1, and an outlet nozzle 8 is provided at the side of the barrel. A cover gas space 10 is formed between the coolant liquid level 9 and the shielding plug 4. An annular gap 11 is formed between the furnace vessel 1 and the shielding plug 4. A plurality of convection prevention beads 20 described below are attached in the height direction of this annular gap 11.

第2図に示すように周方向には数分割されたべa−ズ2
0が設けられる。このぺa−ズ20の一端はしやへいプ
ラグ4に固定具21により固定され、他端部はしやへい
プラグ4に固定具22により固定した支持板23により
、軸方向に移動可能に支持されている。ぺa−ズ20の
自由時の高さは、炉容器1としやへいプラグ4の最大間
隙幅よりわずかに大きくしておき、べa−ズ20の頂部
は常に炉容器1の内壁に軽く圧接させた状態にて設置す
る。
As shown in Fig. 2, the bead 2 is divided into several parts in the circumferential direction.
0 is set. One end of this pair 20 is fixed to the shield plug 4 with a fixture 21, and the other end is supported movably in the axial direction by a support plate 23 fixed to the shield plug 4 with a fixture 22. has been done. The free height of the beads 20 is set slightly larger than the maximum gap width between the furnace vessel 1 and the shielding plug 4, and the top of the beads 20 is always lightly pressed against the inner wall of the furnace vessel 1. Install it in the same position.

上記のように構成された原子炉において、炉容器lとし
やへいプラグ4の間隙幅が運転時の熱膨張差又は寸法差
により周方向に変動しても、べa−ズ20が周方向に分
割構造であるので、182図に破線で示す如く、接触部
のぺa−ズ20が一部高さ方向に移動することにより、
半径方向の変位が吸収可能となり、ベローズ20は常に
炉容器1と椿することになる。よって、環状間隙部8に
おけるカバーガス自然対流は、ぺa−ズ20により閉塞
され発達できず、自然対流による炉容器及びしやへいプ
ラグの不均一な温度分布は十分に緩和される。
In the reactor configured as described above, even if the width of the gap between the reactor vessel l and the shield plug 4 fluctuates in the circumferential direction due to the thermal expansion difference or dimensional difference during operation, the bead 20 remains in the circumferential direction. Since it is a split structure, the pair 20 of the contact part partially moves in the height direction, as shown by the broken line in Fig. 182.
Radial displacements can be absorbed, and the bellows 20 will always be in contact with the furnace vessel 1. Therefore, the natural convection of the cover gas in the annular gap 8 is blocked by the pears 20 and cannot develop, and the uneven temperature distribution in the furnace vessel and the cooling plug caused by the natural convection is sufficiently alleviated.

以上説明のように、本発明によれば炉容器とじゃへいプ
ラグ間隙部に発生する自然対流を抑制でき、自然対流に
起因する炉容器およびしやへいプラグの周方向の大きな
温度分布、熱応力お上び熱変形を緩和し、信頼性の高い
原子炉を得ることができる。さらに、自然対流が抑制さ
れるのでカバーガス対流に伴い間隙部へ移行する冷却材
蒸気の付着も制限される効果も持っている。
As explained above, according to the present invention, natural convection occurring in the gap between the furnace vessel and the shield plug can be suppressed, and the large temperature distribution and thermal stress in the circumferential direction of the furnace vessel and the shield plug caused by natural convection can be suppressed. This makes it possible to alleviate thermal deformation and obtain a highly reliable nuclear reactor. Furthermore, since natural convection is suppressed, it also has the effect of restricting the adhesion of coolant vapor that migrates to the gap due to cover gas convection.

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

@1図は本発明の一実施例による原子炉の縦断面図、@
2図は第1図の対流防止ぺa−ズ部の縦断面図である。 l・・・炉容器、     2・・・炉心、4・・・し
やへいプラグ、 11・・・環状間隙部。 20・・・ぺa−ズ。 (7317)代理人 弁理士 則 近 憲 佑(ほか1
名) 第1図 第2図 2 501−
@Figure 1 is a vertical cross-sectional view of a nuclear reactor according to an embodiment of the present invention, @
FIG. 2 is a longitudinal cross-sectional view of the convection prevention pair of FIG. 1. l...Reactor vessel, 2...Reactor core, 4...Shiyahei plug, 11...Annular gap portion. 20...peas. (7317) Agent Patent Attorney Noriyuki Chika (and 1 others)
Figure 1 Figure 2 Figure 2 501-

Claims (1)

【特許請求の範囲】 1り原子炉炉心と、この炉心を収納し上方が開口した原
子炉容器と、この原子炉容器の開口部を閉塞するしやへ
いプラグとを有する高速増殖型の原子炉において、前記
原子炉容器としやへいプラグとの間に形成された間隙部
に一端なしやへいプラグ外周に固定し他端部をしやへい
プラグに固定された支持板により軸方向に移動可能に支
持し、頂部を炉容器壁に接触させた対流防止べa−ズを
環状間隙部壽学寺鳴に取付けたことを特徴とする原子炉
。 (2)上記べa−ズな周方向分割構造としたことを特徴
とする特許請求の範囲第1項記載の原子炉。
[Scope of Claims] A fast breeder type nuclear reactor that has a nuclear reactor core, a reactor vessel that houses the reactor core and is open at the top, and a shield plug that closes the opening of the reactor vessel. , one end is fixed to the outer periphery of the shield plug in the gap formed between the reactor vessel and the shield plug, and the other end is fixed to the shield plug so as to be movable in the axial direction by a support plate. 1. A nuclear reactor characterized in that a convection prevention bead with its top part in contact with the wall of the reactor vessel is attached to the annular gap. (2) The nuclear reactor according to claim 1, characterized in that it has the base-like circumferentially divided structure.
JP56143785A 1981-09-14 1981-09-14 Reactor Pending JPS5845595A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56143785A JPS5845595A (en) 1981-09-14 1981-09-14 Reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56143785A JPS5845595A (en) 1981-09-14 1981-09-14 Reactor

Publications (1)

Publication Number Publication Date
JPS5845595A true JPS5845595A (en) 1983-03-16

Family

ID=15346937

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56143785A Pending JPS5845595A (en) 1981-09-14 1981-09-14 Reactor

Country Status (1)

Country Link
JP (1) JPS5845595A (en)

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5014306A (en) * 1973-06-07 1975-02-14

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5014306A (en) * 1973-06-07 1975-02-14

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