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JPS6140356B2 - - Google Patents
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JPS6140356B2 - - Google Patents

Info

Publication number
JPS6140356B2
JPS6140356B2 JP56068180A JP6818081A JPS6140356B2 JP S6140356 B2 JPS6140356 B2 JP S6140356B2 JP 56068180 A JP56068180 A JP 56068180A JP 6818081 A JP6818081 A JP 6818081A JP S6140356 B2 JPS6140356 B2 JP S6140356B2
Authority
JP
Japan
Prior art keywords
stopper
rod
core
reactor
operating
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
JP56068180A
Other languages
Japanese (ja)
Other versions
JPS57182695A (en
Inventor
Shigeru Yamaguchi
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.)
Mitsubishi Power Ltd
Original Assignee
Babcock Hitachi KK
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 Babcock Hitachi KK filed Critical Babcock Hitachi KK
Priority to JP56068180A priority Critical patent/JPS57182695A/en
Publication of JPS57182695A publication Critical patent/JPS57182695A/en
Publication of JPS6140356B2 publication Critical patent/JPS6140356B2/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

  • Muffle Furnaces And Rotary Kilns (AREA)

Description

【発明の詳細な説明】 この発明は熱による黒鉛ブロツクの変位を防止
する炉内拘束装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an in-furnace restraint device for preventing displacement of a graphite block due to heat.

従来のガス冷却炉を改善して経済性の向上を図
つたものとして高温ガス炉があるが、この高温ガ
ス炉は出口冷却材温度が1000℃と高温なために金
属製容器内に黒鉛ブロツクを積み立てて炉心およ
び炉心周辺部を構成している。
High-temperature gas furnaces are an improvement over conventional gas-cooled furnaces to make them more economical, but because the outlet coolant temperature of these high-temperature gas furnaces is as high as 1000°C, graphite blocks are placed inside the metal container. They are stacked together to form the core and the surrounding area.

従来の高温ガス炉の構造を第1図に示す。燃料
ブロツク1はプレナムブロツク2で支持されその
重量はプレナムブロツク2の1個あたり3本のポ
スト3を介して断熱ブロツク4へ伝達される これら炉心ブロツクは反射体である黒鉛ブロツ
ク5で周囲を囲まれている。この黒鉛ブロツク5
はその周囲を取囲む金属製のコアバレル6に取り
付けられた、ストツパ7を介して地震時の水平方
向変位が拘束されている。これら炉心構成物は全
体が支持プレート8上に載置され、さらにその重
量はダイヤグリツト9,ブラケツト10を介して
原子炉圧力容器11へ伝達される。上記構造にお
いて、黒鉛の熱膨張係数は、金属の熱膨張係数に
くらべ約1/5程度であるため原子炉運転状態で支
持プレート8,コアバレル6の熱膨張量が反射体
等の黒鉛ブロツクの熱膨張量より大きくなり、黒
鉛ブロツク間および反射体とストツパ間に隙間が
生じる。
The structure of a conventional high-temperature gas furnace is shown in Figure 1. The fuel block 1 is supported by a plenum block 2, and its weight is transmitted to the insulation block 4 through three posts 3 per plenum block 2.These core blocks are surrounded by graphite blocks 5, which are reflectors. It is. This graphite block 5
horizontal displacement during an earthquake is restrained via a stopper 7 attached to a metal core barrel 6 surrounding it. These reactor core components are entirely placed on a support plate 8, and their weight is further transmitted to the reactor pressure vessel 11 via a diagram 9 and a bracket 10. In the above structure, the coefficient of thermal expansion of graphite is about 1/5 of that of metal, so the amount of thermal expansion of the support plate 8 and core barrel 6 during reactor operation is due to the heat of the graphite block such as the reflector. This becomes larger than the amount of expansion, and gaps are created between the graphite blocks and between the reflector and the stopper.

第2図は原子炉運転時の状態を示し、黒鉛ブロ
ツク5とストツパ7の間には隙間W1が、プレナ
ムブロツク2と黒鉛ブロツク5の間には隙間W3
が、断熱ブロツク4相互間には隙間W4が各々生
じてしまう。このため地震等により圧力容器に振
動が加えられると各ブロツクが相互に衝突してブ
ロツクが破損したり、制御棒の挿入が困難となつ
て大事故を生ずる虞れがある。
Figure 2 shows the state of the reactor during operation, with a gap W1 between graphite block 5 and stopper 7, and a gap W3 between plenum block 2 and graphite block 5.
However, gaps W4 are created between the heat insulating blocks 4. For this reason, when vibrations are applied to the pressure vessel due to an earthquake or the like, there is a risk that the blocks will collide with each other, causing damage to the blocks or making it difficult to insert the control rods, resulting in a major accident.

この発明の目的は上述した問題点を除去し、前
述した部分に隙間を生じないよう炉心を拘束し原
子炉の安全性を高める炉心拘束装置を提供するこ
とにある。
SUMMARY OF THE INVENTION An object of the present invention is to provide a core restraint device that eliminates the above-mentioned problems and restrains the core so that no gaps are created in the above-mentioned portions, thereby increasing the safety of the nuclear reactor.

要するにこの発明はコアバレルとストツパに
各々作動桿を回動自在に取り付け、この二本の作
動桿の他端を相互に連結し、この連結部に対して
熱膨張係数の大きな金属から成る棒状体の押圧部
を配置し、原子炉の運転時には金属棒の膨張を前
記作動桿を介してストツパに伝達し、ストツパに
より炉心を拘束するよう構成したものである。
In short, this invention rotatably attaches an operating rod to a core barrel and a stopper, connects the other ends of these two operating rods, and connects a rod-shaped body made of a metal with a large coefficient of thermal expansion to this connecting portion. A pressing portion is arranged so that the expansion of the metal rod is transmitted to the stopper via the operating rod during operation of the nuclear reactor, and the reactor core is restrained by the stopper.

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

第3図および第4図において、12aおよび1
2bは作動桿であつて、作動桿12aの一端はス
トツパ7に、作動桿12bの一端はコアバレル6
に各々回転自在に取り付けてある。20はこれら
作動桿12aおよび12bの自由端を連結した連
結部であつて、各作動桿12a,12bの長さの
合計はこれら作動桿の取り付け位置間の距離Wよ
りも長く形成してあるので、両作動桿を連結する
ことにより全体として略「く」の字形のリンク機
構が形成される。符号13はストツパ7を摺動さ
せる摺動板である。
3 and 4, 12a and 1
2b is an operating rod, one end of the operating rod 12a is connected to the stopper 7, and one end of the operating rod 12b is connected to the core barrel 6.
are rotatably attached to each. Reference numeral 20 is a connecting portion connecting the free ends of these operating rods 12a and 12b, and the total length of each operating rod 12a, 12b is formed to be longer than the distance W between the mounting positions of these operating rods. By connecting the two operating rods, a generally dogleg-shaped link mechanism is formed as a whole. Reference numeral 13 is a sliding plate on which the stopper 7 slides.

次に14は熱膨張係数の大きな金属から成る棒
状体で、好適にはコアバレル6よりも熱膨張係数
の大きな金属で構成する。例えばコアバレル6の
構成金属が低合金鋼である場合には棒状体14は
ステンレス鋼が好適である。
Next, reference numeral 14 denotes a rod-shaped body made of a metal having a large coefficient of thermal expansion, preferably a metal having a coefficient of thermal expansion larger than that of the core barrel 6. For example, when the constituent metal of the core barrel 6 is low alloy steel, the rod-shaped body 14 is preferably made of stainless steel.

前記リンク機構の連結部20はこの棒状体14
に形成した押圧部21に載置された状態となつて
いる。
The connecting portion 20 of the link mechanism is connected to this rod-shaped body 14.
It is in a state where it is placed on a pressing part 21 formed in .

第5図および第6図は以上に説明した装置の作
動状態を示す。第5図は原子炉停止時の状態を、
第6図は原子炉運転時の状態を示す。
5 and 6 show the operating state of the device described above. Figure 5 shows the state when the reactor is shut down.
Figure 6 shows the state during reactor operation.

先ず運転停止時の作動桿12aと12bのなす
角をα、各作動桿の取付部間の距離をWとする原
子炉の運転を開始すると炉内の熱により棒状体1
4はX方向に膨張し、これにより作動桿12a,
12bの連結部20は同方向に押し上げられ、前
記取付部間の距離WはW1に拡大されてストツパ
7をY方向に移動させる。このストツパ7の押圧
力により黒鉛ブロツク5がコアバレル6側に移動
するのを防止する。これら炉内拘束装置は黒鉛ブ
ロツク5により形成された壁面とコアバレルの間
に形成された環状空間内に複数基配置することに
より炉心を効果的に拘束する。
First, when the reactor starts operating, the angle between the operating rods 12a and 12b at the time of shutdown is α, and the distance between the attachment parts of each operating rod is W, the rod-shaped body 1 is
4 expands in the X direction, which causes the actuating rods 12a,
The connecting portions 20 of 12b are pushed up in the same direction, the distance W between the attachment portions is increased to W1 , and the stopper 7 is moved in the Y direction. The pressing force of the stopper 7 prevents the graphite block 5 from moving toward the core barrel 6 side. A plurality of these in-core restraint devices are arranged within the annular space formed between the wall surface formed by the graphite block 5 and the core barrel to effectively restrain the core.

この発明を実施することにより炉内の構成材料
の熱膨張に関係なく常時黒鉛ブロツクの変位を拘
束できるので原子炉の運転を安全に行うことがで
きる。
By carrying out this invention, the displacement of the graphite block can be restrained at all times regardless of the thermal expansion of the constituent materials within the reactor, so that the nuclear reactor can be operated safely.

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

第1図は高温ガス炉の一部破断斜視図、第2図
は高温ガス炉内の構造を示す斜視図、第3図はこ
の発明に係る炉内拘束装置の側面図、第4図は第
3図のA―A視図、第5図は原子炉運転停止時の
炉内拘束装置の側面図、第6図は原子炉運転時の
炉内拘束装置の側面図である。 5……黒鉛ブロツク、6……コアバレル、7…
…ストツパ、12a,12b……作動桿、14…
…棒状体、20……連結部、21……押圧部。
FIG. 1 is a partially cutaway perspective view of a high-temperature gas furnace, FIG. 2 is a perspective view showing the structure inside the high-temperature gas furnace, FIG. 3 is a side view of the in-furnace restraint device according to the present invention, and FIG. 3 is an AA view, FIG. 5 is a side view of the in-core restraint device when the reactor is stopped, and FIG. 6 is a side view of the in-core restraint device when the reactor is in operation. 5...graphite block, 6...core barrel, 7...
...stopper, 12a, 12b...operating rod, 14...
... Rod-shaped body, 20 ... Connection part, 21 ... Pressing part.

Claims (1)

【特許請求の範囲】[Claims] 1 黒鉛ブロツクを押圧するストツパとコアバレ
ルとに各々作動桿の一端を回動自在に取り付け、
これら二本の作動桿の自由端を連結することによ
りストツパとコアバレルの間に略「く」の字形の
リンク機構を介在形成し、このリンク機構の連結
部に棒状体の押圧部を配置することにより棒状体
の膨張力をリンク機構、ストツパを介して黒鉛ブ
ロツク拘束用に使用することを特徴とする炉心拘
束装置。
1 One end of the operating rod is rotatably attached to the stopper that presses the graphite block and the core barrel, respectively.
By connecting the free ends of these two operating rods, a substantially dogleg-shaped link mechanism is interposed between the stopper and the core barrel, and a rod-shaped pressing portion is arranged at the connecting portion of this link mechanism. A core restraint device characterized in that the expansion force of a rod-shaped body is used for restraining a graphite block through a link mechanism and a stopper.
JP56068180A 1981-05-08 1981-05-08 Reactor core restrictive device Granted JPS57182695A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56068180A JPS57182695A (en) 1981-05-08 1981-05-08 Reactor core restrictive device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56068180A JPS57182695A (en) 1981-05-08 1981-05-08 Reactor core restrictive device

Publications (2)

Publication Number Publication Date
JPS57182695A JPS57182695A (en) 1982-11-10
JPS6140356B2 true JPS6140356B2 (en) 1986-09-09

Family

ID=13366316

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56068180A Granted JPS57182695A (en) 1981-05-08 1981-05-08 Reactor core restrictive device

Country Status (1)

Country Link
JP (1) JPS57182695A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5772327B2 (en) * 2011-07-19 2015-09-02 富士電機株式会社 HTGR core restraint mechanism

Also Published As

Publication number Publication date
JPS57182695A (en) 1982-11-10

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