JPS6249953B2 - - Google Patents

Info

Publication number
JPS6249953B2
JPS6249953B2 JP54132837A JP13283779A JPS6249953B2 JP S6249953 B2 JPS6249953 B2 JP S6249953B2 JP 54132837 A JP54132837 A JP 54132837A JP 13283779 A JP13283779 A JP 13283779A JP S6249953 B2 JPS6249953 B2 JP S6249953B2
Authority
JP
Japan
Prior art keywords
plug
furnace vessel
vessel body
heat
reactor vessel
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.)
Expired
Application number
JP54132837A
Other languages
Japanese (ja)
Other versions
JPS5657990A (en
Inventor
Kenji Azuma
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 JP13283779A priority Critical patent/JPS5657990A/en
Publication of JPS5657990A publication Critical patent/JPS5657990A/en
Publication of JPS6249953B2 publication Critical patent/JPS6249953B2/ja
Granted 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は液体金属冷却形原子炉の冷却材液面上
カバーガス領域における容器壁の温度を均一化し
た原子炉容器に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor vessel in which the temperature of the vessel wall in the cover gas region above the coolant liquid level of a liquid metal cooled nuclear reactor is made uniform.

液体金属冷却形原子炉において、炉心および冷
却材を内包する炉容器本体1は通常第1図に示す
ごとくペデスタル2の上に設置され、炉容器本体
1の上部の開口の内側にしやへいプラグ5(通常
は回転機能を持たない固定プラグ)が嵌合して組
立てられている。このため、炉容器本体1としや
へいプラグ外周面51との間には、該両者の製作
公差や組立上の要求から定まるある大きさ以上の
間隙を持たせる必要がある。通常この大きさは数
十mmのオーダの値となるため次の様な問題が発生
する。
In a liquid metal cooled nuclear reactor, a reactor vessel body 1 containing a reactor core and coolant is usually installed on a pedestal 2 as shown in FIG. (Usually a fixed plug that does not have a rotating function) is fitted and assembled. For this reason, it is necessary to provide a gap of a certain size or more between the furnace vessel body 1 and the outer circumferential surface of the shrinkage plug 51, which is determined by manufacturing tolerances and assembly requirements between the two. Normally, this size is on the order of several tens of millimeters, which causes the following problems.

(1) この環状隙間(第1図A部)で炉容器本体1
内のカバーガスが周方向流れを生じ、このため
炉容器本体1およびしやへいプラグ外周面51
の壁温が周方向で異なつた値を示す。これまで
得られている知見によれば、この温度差は40〜
50℃をこす程度の大きさになるものと推定され
る。炉容器本体1の周方向に温度差が生じる
と、熱変形により中心軸に対して曲りを生ずる
ので、原子炉を停止させる際、制御棒を炉心に
挿入する能力が低減されるおそれがある。その
ため一般にこの曲りを拘束するために炉容器本
体1を下部の適当な位置で径方向に固定する設
計をとつているが、それでもこの程度の周方向
温度差が生じると、炉容器本体1の壁が低温の
方位側で圧縮力により座屈するおそれが生じ
る。
(1) At this annular gap (part A in Figure 1), the furnace vessel body 1
The cover gas inside generates a circumferential flow, which causes the furnace vessel body 1 and the outer circumferential surface 51 of the shrink plug to
The wall temperature shows different values in the circumferential direction. According to the knowledge obtained so far, this temperature difference is 40~
It is estimated that it will be about the size of 50 degrees Celsius. If a temperature difference occurs in the circumferential direction of the reactor vessel body 1, thermal deformation causes bending with respect to the central axis, which may reduce the ability to insert control rods into the reactor core when shutting down the reactor. Therefore, in order to restrain this bending, the furnace vessel body 1 is generally designed to be fixed in the radial direction at an appropriate position at the bottom, but even so, if such a circumferential temperature difference occurs, the wall of the furnace vessel body 1 There is a risk of buckling due to compressive force on the colder side.

その上周方向温度分布による熱応力も加算さ
れるため、原子炉容器上部の強度設計が著しく
困難になつてくる。
Since the thermal stress caused by the temperature distribution in the upper circumferential direction is also added, it becomes extremely difficult to design the strength of the upper part of the reactor vessel.

(2) この環状隙間を通して炉心からの中性子が漏
洩するためしやへいプラグ5,6の上方の放射
線量強さを規定値以下におさえるためには、上
方に必要な追加しやへい体を設置するか又はこ
の隙間にしやへい体を挿入する必要がある。
(2) Neutrons leak from the core through this annular gap, so in order to keep the radiation intensity above the shield plugs 5 and 6 below the specified value, install the necessary additional shields above. Otherwise, it is necessary to insert a shield into this gap.

(3) しやへいプラグは、放射線しやへい、熱しや
へい、機器搭載機能等からの要求のため、重量
の重い機器となる所から熱慣性も必然的に大き
くなる。原子炉の起動、停止やスクラム時その
他の過渡状態において原子炉冷却材温度が過渡
的に変化するので、それに伴なつて炉容器本体
1の壁面温度も変化する。この時、炉容器本体
1の内側が熱慣性の大きいしやへいプラグと直
面していると、しやへいプラグ側の温度が急速
に変化しないため、ここが低温ヒートシンクと
して作用し、炉容器本体1が単体の場合にくら
べて、容器本体1の壁面の軸方向温度勾配が増
大する。このため炉容器本体1の熱応力が大き
くなるので炉容器本体上部の強度設計が著しく
困難になつてくる。
(3) Because thermal plugs are required for radiation radiation, heat radiation, equipment mounting functions, etc., their thermal inertia is inevitably large as they are heavy devices. Since the reactor coolant temperature changes transiently during startup, shutdown, scram, and other transient states of the reactor, the wall temperature of the reactor vessel body 1 also changes accordingly. At this time, if the inside of the reactor vessel body 1 is facing the heat sink plug with large thermal inertia, the temperature on the heat sink side does not change rapidly, so this acts as a low-temperature heat sink, and the reactor vessel body The temperature gradient in the axial direction on the wall surface of the container body 1 increases compared to when the container body 1 is a single unit. For this reason, the thermal stress of the furnace vessel body 1 increases, making it extremely difficult to design the strength of the upper part of the furnace vessel body.

以上の如き種々の問題があるため、炉容器本体
の上部としやへいプラグの嵌合部の構造に関して
は、相互の間隙を小さくし、中性子ストリーミン
グをおさえこみ、かつしやへいプラグと炉容器本
体間にある程度の断熱効果をもたせることが望ま
しい。そのために第1図のA部で示す円環状間隙
に断熱体を挿入することが考えられるがそれだけ
では、双方の胴の製作公差、組立のためのクリア
ランス等の制約上、やはり一定量のギヤツプがで
きるため問題の根本的解決にはならず特別な対策
手段が必要性となる。
Due to the various problems mentioned above, regarding the structure of the fitting part of the upper part of the reactor vessel body and the shield plug, it is necessary to reduce the gap between them and suppress neutron streaming. It is desirable to have some degree of insulation effect between them. To this end, it may be possible to insert a heat insulator into the annular gap shown in part A in Figure 1, but this alone would still require a certain amount of gap due to constraints such as manufacturing tolerances for both shells and clearance for assembly. However, this does not fundamentally solve the problem and requires special countermeasures.

本発明は上記の必要性を満たすためになされた
もので、しやへいプラグ外周面と炉容器本体の上
部の形状を考慮した上で断熱体を挿入すること
で、上述の諸問題点の解決をはかつた原子炉容器
を提供することを目的とする。
The present invention has been made to meet the above-mentioned needs, and solves the above-mentioned problems by inserting a heat insulator in consideration of the shape of the outer peripheral surface of the shield plug and the upper part of the furnace vessel body. The purpose is to provide a nuclear reactor vessel with

以下図面を参照して本発明の一実施例を説明す
る。第1図は従来の原子炉容器の全体を概略的に
示すもので、第2図は本発明の要部を示すもので
ある。すなわち、炉容器本体1は冷却材3を内包
し、上部に固定しやへいプラグ5や回転しやへい
プラグ6が設置されて蓋の役目をはたし、内部に
は通常アルゴン等の不活性ガスからなるカバーガ
ス4を封入している。
An embodiment of the present invention will be described below with reference to the drawings. FIG. 1 schematically shows the entire conventional nuclear reactor vessel, and FIG. 2 shows the main parts of the present invention. That is, the reactor vessel main body 1 contains a coolant 3, a fixed hard plug 5 and a rotatable hard plug 6 are installed at the top to serve as a lid, and the inside is usually filled with inert gas such as argon. A cover gas 4 made of gas is sealed.

炉容器本体1の上部に傾斜面を設けて円錐状と
し、円錐面に例えばステンレス鋼のウール等の断
熱体7をしき詰めステンレス板(7に含む)を上
に当接して、さらにその上を断熱体支持具8で、
ボルト等により取付ける。該支持具8は例えば第
3図に示す様なセクタ状になつており弾性にとん
でいる。一方該支持具8の下端は、炉容器本体1
に設けられたストツパ11の内部に嵌め込まれて
いる。
The upper part of the furnace vessel main body 1 is provided with an inclined surface to form a conical shape, and the conical surface is filled with a heat insulating material 7 such as stainless steel wool, and a stainless steel plate (included in 7) is placed on top of the conical surface. With the insulation support 8,
Attach with bolts, etc. The support 8 has a sector shape as shown in FIG. 3, for example, and is elastic. On the other hand, the lower end of the support 8 is connected to the furnace vessel main body 1
It is fitted into the inside of a stopper 11 provided in the.

そして該支持具8で形成される円錐面に、相対
する位置に、しやへいプラグ外周面51が据付け
られる。なお図では双方の胴共円錐状となつてい
るが、いずれか一方のみを円錐状とすることも設
計工夫によつては可能である。この面は少くとも
一方が円錐状となつているため、しやへいプラグ
5を組込むさいには、必要な作業スペースが確保
されるし、又該二胴の製作公差分は、断熱体7お
よび断熱体支持具8自体の弾性により吸収しなが
ら、双方の胴を軽く接触状態とすることができ
る。
A stiff plug outer circumferential surface 51 is installed at a position facing the conical surface formed by the support 8. In the figure, both bodies are conical, but it is also possible to make only one of them conical, depending on the design. Since at least one side of this surface is conical, the necessary work space is secured when installing the insulation plug 5, and the manufacturing tolerance of the two cylinders is such that the insulation body 7 and While absorbing the heat due to the elasticity of the heat insulator support 8 itself, both bodies can be brought into a light contact state.

以上説明のように本発明の原子炉容器はしやへ
いプラグ外側胴とのギヤツプを、クリアランスが
ほとんどなく軽い接触状態とすることができるた
め前述した問題点の(1)項の周辺流れによる温度不
均一現状を阻止できるし、又断熱体の材質選定に
より(2)項の中性子ストリーミング低減に有効であ
る。さらにしやへいプラグと炉容器間の熱授受を
制限することができるために(3)項の過渡温度変化
時の炉容器の軸方向温度勾配も十分低減すること
ができるため、十分な強度を有する原子炉容器を
提供できる。
As explained above, the reactor vessel of the present invention can be in a light contact state with almost no clearance between the gap and the outer shell of the thin plug. This can prevent the non-uniform situation, and is effective in reducing neutron streaming in item (2) by selecting the material for the heat insulator. Furthermore, since it is possible to limit the heat exchange between the heat exchanger plug and the furnace vessel, it is possible to sufficiently reduce the axial temperature gradient of the furnace vessel during the transient temperature change described in (3). It is possible to provide a nuclear reactor vessel with

また円錐形状を採用したことにより、炉容器本
体の製作公差や組立上のギヤツプ確保の問題も同
時に解決できている。
In addition, by adopting a conical shape, we were also able to solve the problem of manufacturing tolerances for the furnace vessel body and securing gaps during assembly.

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

第1図は従来の原子炉容器を1部側面で示す縦
断面図、第2図は本発明に係る原子炉容器の要部
のみを部分的に示す縦断面図、第3図は第2図に
おけるA部を拡大して示す斜視図である。 1;炉容器本体、5;しやへいプラグ(固定プ
ラグ)、51;しやへいプラグ外周面、52;プ
レート、7;断熱体、8;断熱体支持具。
FIG. 1 is a vertical cross-sectional view showing a part of a conventional reactor vessel from the side, FIG. 2 is a vertical cross-sectional view partially showing only the main parts of the reactor vessel according to the present invention, and FIG. It is a perspective view which expands and shows the A section in FIG. 1; Furnace vessel main body, 5; Shiyahei plug (fixed plug), 51; Shiyahei plug outer peripheral surface, 52; Plate, 7; Heat insulating body, 8; Heat insulating body support.

Claims (1)

【特許請求の範囲】[Claims] 1 炉容器本体と、この炉容器本体の上部開口を
閉塞するしやへいプラグと、このしやへいプラグ
の外周面と前記炉容器本体との間に介在した断熱
体と、この断熱体を支持するための可撓性支持具
とを具備し、断熱体と炉容器本体との接触面およ
び断熱体としやへいプラグとの接触面の内少なく
とも一方の接触面を円錐状に形成してなることを
特徴とする原子炉容器。
1. A furnace vessel body, a shield plug that closes the upper opening of the furnace vessel body, a heat insulating body interposed between the outer peripheral surface of the cold plug and the furnace vessel body, and a heat insulating body that supports the heat insulating body. and a flexible support for the heating, and at least one of the contact surfaces between the heat insulator and the furnace vessel body and the contact surface between the heat insulator and the insulation plug is formed into a conical shape. A nuclear reactor vessel featuring:
JP13283779A 1979-10-17 1979-10-17 Nuclear reactor vessel Granted JPS5657990A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP13283779A JPS5657990A (en) 1979-10-17 1979-10-17 Nuclear reactor vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP13283779A JPS5657990A (en) 1979-10-17 1979-10-17 Nuclear reactor vessel

Publications (2)

Publication Number Publication Date
JPS5657990A JPS5657990A (en) 1981-05-20
JPS6249953B2 true JPS6249953B2 (en) 1987-10-22

Family

ID=15090673

Family Applications (1)

Application Number Title Priority Date Filing Date
JP13283779A Granted JPS5657990A (en) 1979-10-17 1979-10-17 Nuclear reactor vessel

Country Status (1)

Country Link
JP (1) JPS5657990A (en)

Also Published As

Publication number Publication date
JPS5657990A (en) 1981-05-20

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