JPH0219792A - Upper mechanism of reactor core - Google Patents

Upper mechanism of reactor core

Info

Publication number
JPH0219792A
JPH0219792A JP63169018A JP16901888A JPH0219792A JP H0219792 A JPH0219792 A JP H0219792A JP 63169018 A JP63169018 A JP 63169018A JP 16901888 A JP16901888 A JP 16901888A JP H0219792 A JPH0219792 A JP H0219792A
Authority
JP
Japan
Prior art keywords
coolant
drum
temperature
shell
generated
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
JP63169018A
Other languages
Japanese (ja)
Inventor
Ichiro Yoshimura
一郎 吉村
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 JP63169018A priority Critical patent/JPH0219792A/en
Publication of JPH0219792A publication Critical patent/JPH0219792A/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

PURPOSE:To maintain thermal stress below a correct value even if a temperature of a coolant is varied suddenly by providing an outer drum on the outside peripheral part of a drum and providing plural flow holes for penetrating the drum on the upper and the lower parts of the drum. CONSTITUTION:This mechanism 25 contains a control rod driving device therein, and has a drum 37 for penetrating a free liquid level 40 of a cover gas and a coolant 14. In this state, when a temperature of the coolant 14 is varied suddenly at the time of tripping a nuclear reactor, the coolant 14 of an annular part 52 of the inside of an outer drum 38 is brought to temperature fall a little later than that of the outside, as well, and a temperature difference is generated between this coolant and that of the inside of the drum 37. By flow holes 50, 51 of the upper and the lower parts of this drum 37, these coolants 14 are allowed to communicate with each other, therefore, a natural convection is generated. In such a way, the quantity of the coolant 14 of the annular part 52 is sufficiently smaller than that of the inside and a difference of the heat capacity is also large, and the coolant 14 which scarcely causes a temperature fall for many hours flows out of the hole 50. Accordingly, a variation of a temperature distribution in the vicinity of the liquid level 40 of the drum 37 becomes slow, and generated thermal stress is also reduced.

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) この発明は、炉心から流出する冷却材が胴の内部に直接
流入せずに、胴の外部を流れる高速増殖炉の炉心上部機
構に関する。
[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) This invention provides a fast breeder reactor core in which coolant flowing out from the core flows outside the shell instead of flowing directly into the interior of the shell. Regarding the upper mechanism.

(従来の技術) 高速増殖炉の炉心上部機構は制御棒、制御棒駆動機構、
制御棒案内管および計装ウェル並びに整流装置等を装備
して構成される。
(Prior art) The upper core mechanism of a fast breeder reactor consists of control rods, control rod drive mechanism,
It is equipped with a control rod guide tube, instrumentation well, rectifier, etc.

第5図に示すように、整流装置33は炉心上部機構25
の胴37の下部に取付けられ、上記他の機器は胴37の
内部に収納される。
As shown in FIG. 5, the rectifier 33 is connected to the core upper mechanism 25
The other equipment mentioned above is housed inside the body 37.

(発明が解決しようとする課題) 原子炉トリップ時に冷却材温度が急激に変化した場合、
炉心上部機構25の外部の冷却材14は、温度が急激に
低下するが、内部の冷却材温度は外部の冷却材温度に追
従せず高温状態に維持される。
(Problem to be solved by the invention) When the coolant temperature changes suddenly during a reactor trip,
Although the temperature of the coolant 14 outside the core upper mechanism 25 drops rapidly, the temperature of the coolant inside does not follow the temperature of the outside coolant and is maintained at a high temperature.

(第4図参照)。(See Figure 4).

また、しやへいプラグ17およびカバーガス中16に位
置する炉心上部機構25の上部は大きな熱容量と断熱性
により原子炉トリップ前の温度が保持される。
Further, the temperature of the upper part of the core upper mechanism 25 located in the cooling plug 17 and the cover gas 16 is maintained at the temperature before the reactor trip due to its large heat capacity and heat insulation properties.

したがって、胴37の内外において、冷却材に温度差が
生ずると同時に軸方向にも大きな温度勾配が生じる。
Therefore, a temperature difference occurs in the coolant inside and outside the shell 37, and at the same time, a large temperature gradient also occurs in the axial direction.

これらの板厚および軸方向の温度勾配により冷却材14
の自由液面40近傍には、過大な熱応力が発生するため
、従来は熱抵抗を設置する等の構造対応や原子炉の運転
モードを制限するなどの対策が必要であった。
Due to these plate thicknesses and axial temperature gradients, the coolant 14
Because excessive thermal stress occurs near the free liquid level 40 of the reactor, conventional measures have been required such as structural measures such as installing a thermal resistor and restricting the operating mode of the reactor.

また、炉心19に近い整流装置33や胴37の下端部の
接液部も自由液面40近傍よりさらに厳しい温度変化を
受はフレキシブルジヨイント等の構造とする必要があっ
た。
In addition, the liquid-contacted parts of the flow straightener 33 and the lower end of the shell 37 near the core 19 were required to have a structure such as a flexible joint so that they would be able to withstand even more severe temperature changes than those near the free liquid level 40.

この発明は、上記事実を考慮してなされたものであり、
冷却材の温度が急変しても熱応力を適正な値以下に維持
することができる高速増殖炉の炉心上部機構を提供する
ことを目的とする。
This invention was made in consideration of the above facts,
It is an object of the present invention to provide an upper core mechanism for a fast breeder reactor that can maintain thermal stress below an appropriate value even if the temperature of the coolant changes suddenly.

〔発明の構成〕[Structure of the invention]

(課題を解決するための手段) この発明は、制御棒駆動機構等を内包する胴を有する高
速増殖炉の炉心上部機構において、上記用の外周部に外
胴を有し胴の上部と下部に胴を貫通する複数のフローホ
ールを設けたものである。
(Means for Solving the Problems) The present invention provides an upper core mechanism for a fast breeder reactor having a shell containing a control rod drive mechanism, etc., which has an outer shell on the outer periphery for the above purpose, and has an upper and a lower part of the shell. It is equipped with a plurality of flow holes that pass through the body.

(作 用) したがって、この発明に係る高速増殖炉の炉心上部機構
は、外部の冷却材温度が急激に下がった場合、外胴と胴
のアニユラス部の冷却材も冷やされ下降流が生じ下部の
フローホールから川内に流入する。
(Function) Therefore, in the upper core mechanism of the fast breeder reactor according to the present invention, when the temperature of the external coolant suddenly drops, the coolant in the outer shell and the annulus of the shell is also cooled, creating a downward flow, which occurs in the lower part. It flows into the river through the flow hole.

一方、上部のフローホールからは、高温の冷却材がアニ
ユラス部に流出し胴の板厚および軸方向の温度勾配を緩
和する。
On the other hand, high-temperature coolant flows from the upper flow hole to the annulus section, reducing the thickness of the shell and the temperature gradient in the axial direction.

(実施例) 以下、この発明の実施例を図面に基づいて説明する。(Example) Embodiments of the present invention will be described below based on the drawings.

第1図は、この発明に係る高速増殖炉の炉心上部機構2
5における一実施例の要部を破断して示す側面図、第2
図は第1図の実施例が適用された高速増殖炉を示す断面
図である。
FIG. 1 shows a core upper mechanism 2 of a fast breeder reactor according to the present invention.
5 is a side view showing a broken part of the main part of one embodiment in No. 5;
The figure is a sectional view showing a fast breeder reactor to which the embodiment of FIG. 1 is applied.

第2図に示すように、一般に高速増殖炉13は液体ナト
リウム等の液体金属を冷却材14として使用する。この
冷却材14が原子炉容器15内に充填される。
As shown in FIG. 2, a fast breeder reactor 13 generally uses liquid metal such as liquid sodium as a coolant 14. This coolant 14 is filled into the reactor vessel 15 .

この原子炉容器15の上端はしやへいプラグ17によっ
て閉塞され、また原子炉容器15内に炉心19が収容さ
れる。
The upper end of this reactor vessel 15 is closed by a shield plug 17, and a reactor core 19 is accommodated within the reactor vessel 15.

液体ナトリウム等の冷却材14は原子炉容器15の下部
の冷却材人口21が流入し、炉心19内を上方に流れ加
熱され、冷却材出口23から流出するよう構成される。
A coolant 14 such as liquid sodium is configured such that a coolant population 21 in the lower part of the reactor vessel 15 flows into the reactor vessel 15, flows upward in the reactor core 19, is heated, and flows out from a coolant outlet 23.

しやへいプラグ17には炉心上部機構25が取付けられ
る。
A core upper mechanism 25 is attached to the shield plug 17 .

この炉心上部機構25は制御棒、制御棒駆動機構27、
制御棒内管29および計装ウェハ31を内包する胴37
が冷却材14の自由液面40を貫通している。胴37の
下部には整流装置33が取付けられ炉心から流出する冷
却材を分流し原子炉の上部プレナム41に導いている。
This core upper mechanism 25 includes control rods, a control rod drive mechanism 27,
A shell 37 containing the control rod inner tube 29 and the instrumentation wafer 31
penetrates the free liquid surface 40 of the coolant 14. A rectifier 33 is attached to the lower part of the shell 37 to divert the coolant flowing out from the core and guide it to the upper plenum 41 of the reactor.

一方、1洞37の外周部には外胴38がアニユラス部5
2を介して設置され、胴37の熱しゃへい板としてM3
7に加わる温度変化を緩和すると同時に内部に冷却材1
4が容易に流入しないように境界を形成している。
On the other hand, an outer body 38 is attached to the annulus portion 5 on the outer periphery of the first cavity 37.
M3 is installed as a heat shield plate for the shell 37.
At the same time, a coolant 1 is added inside to alleviate the temperature change applied to 7.
The boundary is formed so that 4 does not easily flow in.

原子炉トリップ時等に冷却材温度が急激に変化した場合
には、炉心上部機構25の外部の冷却材14は温度が急
激に変化するが、胴37の内部の冷却材温度は外部の冷
却機温度に追従せず、炉心上部機構の内部と外部には著
しい温度差が生ずる。
When the coolant temperature changes suddenly during a reactor trip, etc., the temperature of the coolant 14 outside the upper core mechanism 25 changes suddenly, but the coolant temperature inside the shell 37 changes due to the temperature of the coolant outside the core upper mechanism 25. It does not follow the temperature, and a significant temperature difference occurs between the inside and outside of the upper core structure.

この過渡状態を詳細に示すと、第3図に示すように外部
の冷却材14に直接に接している外Wi438はこの外
部の冷却材温度によく追従し、外胴38の内側のアニユ
ラス部52の冷却材も少し遅れて温度降下し胴37の内
部の冷却材との間に温度差を生ずる。
To show this transient state in detail, as shown in FIG. The temperature of the coolant also drops with a little delay, creating a temperature difference between the coolant and the coolant inside the shell 37.

胴の上部と下部のフローホール50.51によりこれら
の冷却材は連通しているため、温度差のない時には停留
していたアニユラス部52の冷却材は下降流となり下部
のフローホール51から胆37内に流入し比重差により
15i37内の高温の冷却材を上方へ押上げ下部に溜る
Since these coolants are in communication with each other through the flow holes 50 and 51 in the upper and lower parts of the body, the coolant in the annulus part 52, which was stagnant when there was no temperature difference, flows downward and flows from the flow hole 51 in the lower part to the part 37. Due to the difference in specific gravity, the high temperature coolant inside 15i37 is pushed upwards and accumulates at the bottom.

一方、押上げられた胴37内の冷却材は上部のフローホ
ール50からアニユラス部52へ流出する。
On the other hand, the coolant in the cylinder 37 that has been pushed up flows out from the upper flow hole 50 to the annulus portion 52.

この自然対流の発生により温度分布は次のようになる。Due to the occurrence of this natural convection, the temperature distribution becomes as follows.

第4図に示すようにアニユラス部52の冷却材の量は内
部の冷却材の量に比較して十分に少ないので熱容量の差
も大きく、上部のフローホール50からは長時間にわた
りほとんど温度低下のない冷却材が流出し、胴37の液
面近傍の温度分布の変化は緩慢なものとなり発生する熱
応力も軽減される。
As shown in FIG. 4, the amount of coolant in the annulus section 52 is sufficiently small compared to the amount of coolant inside, so there is a large difference in heat capacity, and the temperature does not drop for a long time from the upper flow hole 50. The remaining coolant flows out, the temperature distribution near the liquid surface of the shell 37 changes slowly, and the generated thermal stress is also reduced.

上部の液面近傍では高温であった冷却材もアニユラス部
52を下降する間に冷やされ低湿になって下部のフロー
ホール51から胴37内に流入するため炉心に近く急激
に温度降下し低温になっている胴37の下部外面と胴3
7内部の温度差を少なくするため、この部分の熱応力も
軽減される。
The coolant, which was at a high temperature near the liquid level in the upper part, is cooled down while descending through the annulus section 52 and becomes low-humidity, and flows into the shell 37 from the flow hole 51 in the lower part, so the temperature rapidly drops near the reactor core and becomes low temperature. The lower outer surface of the trunk 37 and the trunk 3
Since the temperature difference inside 7 is reduced, the thermal stress in this part is also reduced.

〔発明の効果〕〔Effect of the invention〕

以上のように、この発明に係る高速増殖炉の炉心上部機
構によれば、外胴と胴のアニユラス部と胴肉の冷却材が
上下のフローホールにより連通し、原子炉のトリップ時
等の急激な温度変化時に自然対流を生じ、円内外の温度
差を軽減し熱応力を緩和することができる。
As described above, according to the upper core mechanism of a fast breeder reactor according to the present invention, the outer shell, the annulus portion of the shell, and the coolant of the shell are communicated through the upper and lower flow holes, and sudden changes such as when the reactor trips, etc. Natural convection occurs when the temperature changes, reducing the temperature difference between the inside and outside of the circle and alleviating thermal stress.

この軽減効果、すなわち自然対流の強さは外部の冷却材
の温度降下の厳しさに比例すること、外部からの操作が
全く不要であること、また構造が簡素であり本発明を適
用するためには従来の構造にフローホールを追加するの
みであること等その効果は大きい。
This reduction effect, that is, the strength of natural convection is proportional to the severity of the temperature drop of the external coolant, no external operation is required, and the structure is simple, making it possible to apply the present invention. This has great effects, such as simply adding flow holes to the conventional structure.

特に温度差が発生すれば必ず熱応力の緩和効果かえられ
ることは、信頼性の向上にも大きく寄与するものである
In particular, if a temperature difference occurs, the effect of alleviating thermal stress is always changed, which greatly contributes to improving reliability.

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

第1図はこの発明に係る高速増殖炉の炉心上部機構にお
ける実施例の要部を示す断面図、第2図は実施例が適用
された高速増殖炉を示す断面図、13・・・高速増殖 
    25・・・炉心上部機構37−1.胴    
    38・・・外胴50・・・上部フローホーム 
51・・・下部フローホーム52・・・アニユラス部 代理人 弁理士 則 近 憲 佑 同    第子丸   健 第1図 第2図
Fig. 1 is a sectional view showing the main parts of an embodiment of the upper core mechanism of a fast breeder reactor according to the present invention, Fig. 2 is a sectional view showing a fast breeder reactor to which the embodiment is applied, 13...Fast breeder
25... Core upper mechanism 37-1. torso
38... Outer body 50... Upper flow home
51... Lower Flow Home 52... Annulus Department Agent Patent Attorney Nori Chika Ken Yudo Daishimaru Ken Figure 1 Figure 2

Claims (1)

【特許請求の範囲】[Claims] 制御棒駆動機構等を内包しカバーガスと冷却材の自由液
面を貫通する胴を持つ高速増殖炉の炉心上部機構におい
て、内部に停留した冷却材を有する胴と、アニュラス部
を介してその外部に設置される外胴とから構成され、前
記胴の上部と下部に各々複数のフローホールを有する炉
心上部機構。
In the upper core mechanism of a fast breeder reactor, which has a shell that houses the control rod drive mechanism etc. and penetrates the cover gas and the free liquid surface of the coolant, the shell has the coolant stagnant inside, and the outer part of the shell passes through the annulus. An upper core mechanism comprising an outer shell installed in the upper core and a plurality of flow holes in the upper and lower parts of the shell.
JP63169018A 1988-07-08 1988-07-08 Upper mechanism of reactor core Pending JPH0219792A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63169018A JPH0219792A (en) 1988-07-08 1988-07-08 Upper mechanism of reactor core

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63169018A JPH0219792A (en) 1988-07-08 1988-07-08 Upper mechanism of reactor core

Publications (1)

Publication Number Publication Date
JPH0219792A true JPH0219792A (en) 1990-01-23

Family

ID=15878807

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63169018A Pending JPH0219792A (en) 1988-07-08 1988-07-08 Upper mechanism of reactor core

Country Status (1)

Country Link
JP (1) JPH0219792A (en)

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