JPS6073393A - Supporter for apparatus in reactor - Google Patents

Supporter for apparatus in reactor

Info

Publication number
JPS6073393A
JPS6073393A JP58180751A JP18075183A JPS6073393A JP S6073393 A JPS6073393 A JP S6073393A JP 58180751 A JP58180751 A JP 58180751A JP 18075183 A JP18075183 A JP 18075183A JP S6073393 A JPS6073393 A JP S6073393A
Authority
JP
Japan
Prior art keywords
heat exchanger
intermediate heat
holding groove
equipment
stand pipe
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
JP58180751A
Other languages
Japanese (ja)
Inventor
今吉 祥
石倉 修一
耕一 広田
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 Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
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 Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP58180751A priority Critical patent/JPS6073393A/en
Publication of JPS6073393A publication Critical patent/JPS6073393A/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

  • Devices For Medical Bathing And Washing (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】 本発明は、タンク型液体金属高速増殖炉(LMFBR)
における、原子炉容器内機器の支持構造として、径方向
の緩やかな熱変位に対しては抗力を生ぜず、地震時に径
方向の急激な振動に対しては抗力を・生じさせる等、振
れ止め斜面を設けてなる原子炉内接器の支持装置に関す
るものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a tank-type liquid metal fast breeder reactor (LMFBR).
As a support structure for the equipment inside the reactor vessel, the steady slope slope does not generate resistance against gradual thermal displacement in the radial direction, but generates resistance against sudden vibrations in the radial direction during an earthquake. The present invention relates to a support device for a nuclear reactor internal equipment.

従来、原子炉内機器の支持構造は第1図ないし第3図に
示すようになっている。図においてlは原子炉容器、2
はルーフスラブ、3は炉内aイJである中間熱交換器、
4は一次糸ポンプ、5は炉心支持構造、6は炉心上部機
構、7は上部プレナム、8は1部ブレナム、9は隔壁構
造、10は炉心、11は炉内配管、12はマノメーク構
造であり、上記炉心上部様+f¥ 6はルーフスラブ2
から吊り下げられ、炉心10は原子炉容器1から炉心支
持構造5を介して吊や下げられ、炉心を出た冷却材は高
γ1〜にの上1rl(ブレナーム7に流出し、中間熱交
換器3を通ってim: 17i、’、の下部プレナム8
へ流出する。
Conventionally, support structures for equipment inside a nuclear reactor are shown in FIGS. 1 to 3. In the figure, l is the reactor vessel, 2
3 is the roof slab, 3 is the intermediate heat exchanger in the furnace ai J,
4 is a primary thread pump, 5 is a core support structure, 6 is a core upper mechanism, 7 is an upper plenum, 8 is a partial brenum, 9 is a bulkhead structure, 10 is a reactor core, 11 is an in-core piping, and 12 is a manmade structure. , above core upper part +f¥ 6 is roof slab 2
The reactor core 10 is suspended from the reactor vessel 1 via the core support structure 5, and the coolant exiting the core flows into the high 3 through im: 17i,', lower plenum 8
leaks to.

上記1部プレナム8の冷却側は、−次系ポンプ4に吸い
込まオ)、炉内配管11を・通って再ひ炉心10へ送り
込寸れる。
The cooling side of the first part plenum 8 is sucked into the sub-system pump 4) and sent to the reactor core 10 again through the reactor piping 11.

ここで、品温の上部プレナム7から低温の下部プレナム
8への熱損失を最小限に止めるよう隔壁1:1者1□9
がRayけられているので、炉心支持構造は、11ぼ下
部プレナム温度と同等となっている。下部プレナム8し
1上部プレナム7に比べて低温であるとはいえ中間熱交
換器3、−次系ポンプ4の据付面であるルーフスラブの
上面とは約300℃の温度差がある。
Here, the partition wall 1:1 part 1
Since the core support structure has a lower plenum temperature of about 11%. Although the lower plenum 8 is at a lower temperature than the upper plenum 7, there is a temperature difference of about 300° C. from the upper surface of the roof slab, which is the installation surface of the intermediate heat exchanger 3 and secondary pump 4.

上述したような構造において、炉内機器である中間熱交
換器3、−次系ポンプ4、炉心上部機構6、竹に長尺で
ある中間熱交換器3、−次系ポンプ4を単に上部から吊
りTけた片持梁では、地震売件の厳しい我国において、
桔造的に成立する見通しはない。
In the above-described structure, the reactor equipment such as the intermediate heat exchanger 3, secondary pump 4, core upper mechanism 6, long bamboo intermediate heat exchanger 3, and secondary pump 4 are simply connected from the top. In Japan, where earthquake sales are severe, with a suspended T-girder cantilever,
There is no prospect that it will come to fruition.

そこで従来は、中間熱交換器3、−次系月シンフ。Therefore, in the past, the intermediate heat exchanger 3 was used as an intermediate heat exchanger.

4のルーフスラブ2の上面と、炉心支持構造5の中間熱
交換器3、−次系ボッ14貫通部の温度差による熱膨張
変位を吸収でき、しかも中間熱交換器3、−次系ポンプ
4の下部で幾分でも支持効果が期待できるように、マノ
メータ構造1275;考えられていた。
It is possible to absorb thermal expansion displacement caused by a temperature difference between the upper surface of the roof slab 2 of No. 4 and the intermediate heat exchanger 3 of the core support structure 5 and the secondary system box 14 penetration part, and the intermediate heat exchanger 3 and the secondary system pump 4 can be absorbed. The manometer structure 1275 was considered so that some support effect could be expected at the lower part of the structure.

すなわち、上記マノメータ構造12は第2図ないし第3
図に示すように、中間熱交換器3力(仕切円筒13に対
して矢印方向に動いたとすると tp間熱交換器3と、
仕切円筒13のx′力方向隙(111は小さくなシ、×
方向の隙間は犬きくなる。又tま「1コ間熱交換器3と
、外筒14は一体措造となっているので、仕切円筒13
と外筒14の隙間は逆になる。このために中間熱交換器
3、仕切円筒13、外筒14の隙間の流体は矢印一方向
に運動し、流体が運動するためのエネルギーが中間熱交
換器3への抗力となって制振効果が期待されている。
That is, the manometer structure 12 is as shown in FIGS.
As shown in the figure, if the intermediate heat exchanger 3 force (moves in the direction of the arrow with respect to the partition cylinder 13), the intermediate heat exchanger 3 and
The gap in the x′ force direction of the partition cylinder 13 (111 is a small
The gap in the direction becomes dog-like. Also, since the single heat exchanger 3 and the outer cylinder 14 are integrally constructed, the partition cylinder 13
The gap between the outer cylinder 14 and the outer cylinder 14 are reversed. For this reason, the fluid in the gap between the intermediate heat exchanger 3, the partition cylinder 13, and the outer cylinder 14 moves in the direction of the arrow, and the energy for the movement of the fluid becomes a drag force on the intermediate heat exchanger 3, resulting in a vibration damping effect. is expected.

しかしながら、このシステムにおいて、中間熱交換器3
と仕切円筒13、仕切円筒13と外筒14との隙間は、
中間熱交換器3の製作据付精度及び前述した中間熱交換
器3の据付部と炉心支持構造5の貫通部の温度差による
熱膨張変位を考慮すると、各隙間で約100mm程度が
必要になると考えられるため、流路面積が大きく、あま
り制振効果が期待できないことになる。
However, in this system, the intermediate heat exchanger 3
The gap between the partition cylinder 13 and the partition cylinder 13 and the outer cylinder 14 is
Considering the manufacturing and installation accuracy of the intermediate heat exchanger 3 and the thermal expansion displacement due to the temperature difference between the installation part of the intermediate heat exchanger 3 and the penetration part of the core support structure 5 mentioned above, it is thought that approximately 100 mm will be required for each gap. As a result, the flow path area is large and a vibration damping effect cannot be expected to be great.

捷た、」+層1q発生時、仕切円筒13と外筒14の間
の液体ナトリウムが仕切円筒13の上端を越して、中間
熱交換器3と仕切円筒13の隙間に入って廻りこむ流路
以外の流路が生じないように、上部には)leガスM1
6を設け、炉外にてHeガス層16の圧力制御を行なう
システム及び炉内には?rI人′ば15が必要と寿る。
When the layer 1q is generated, the liquid sodium between the partition cylinder 13 and the outer cylinder 14 passes over the upper end of the partition cylinder 13, enters the gap between the intermediate heat exchanger 3 and the partition cylinder 13, and flows around. )le gas M1 at the top so that no flow path other than
6 is installed, and a system for controlling the pressure of the He gas layer 16 outside the furnace and inside the furnace? rI people need 15 years to live.

一方、下部の振れ止めをやめるため、炉内機器の板厚を
増し、剛性を高めることも考えられるが、板厚を増すと
、物Bが増大するたけでなく、」二部プレナムの熱過度
変化による熱応力によって構造が成立たない。
On the other hand, in order to eliminate the steady rest at the bottom, it is possible to increase the plate thickness of the furnace equipment and increase its rigidity, but increasing the plate thickness not only increases the amount of object B, but also increases the thermal stress of the second plenum. The structure cannot be established due to the thermal stress caused by the change.

また、マノメータ構造12(ζおいては、Heガスの圧
力制御装置が必要であり、炉内にも導入管が必要になる
が、その割には制振効果が小さいため、新規な構造の実
現が強く望まれていた。
In addition, the manometer structure 12 (ζ) requires a pressure control device for He gas and an introduction pipe into the furnace, but the vibration damping effect is small, so a new structure was created. was strongly desired.

本発明は、上述した要望に応えるためになされたもので
あり、タンク型LMFBI尤の炉内機器支持構造におい
て、径方向の緩やかな熱度に対しては抗力を生ぜず、地
震時の径方向の急6)kな振動((対しては大きな抗力
を生じさせることを目的とした構造を提供するものであ
る。
The present invention has been made in response to the above-mentioned demands, and in a tank-type LMFBI reactor equipment support structure, it does not generate resistance against gentle heat in the radial direction, and is capable of suppressing radial damage during an earthquake. Sudden 6)k Vibration ((For which the structure is intended to produce a large drag force.

以)、本発明による実施例全第4図ないし第7図に基つ
いて詳細に説fν]する。
Hereinafter, all embodiments according to the present invention will be explained in detail based on FIGS. 4 to 7.

第4図ないし第5図は、本発明における第1の発明を示
す炉内機器としての中間熱交換器の縦断面図、及びA−
A線断面図であり、図において3は従来例と同様に中間
熱交換器、17は、中間熱交換器3用のスタンドパイプ
で下端は図示しない炉心支持構造に固着されている。1
8はボール、19はスタンドパイプの内周面に環状に形
成された保持N’?、20a 、20bは保持溝19の
傾斜面で、軸方向に交1して45°の上向き傾斜を有し
ている。
4 and 5 are longitudinal sectional views of an intermediate heat exchanger as an in-furnace device showing the first aspect of the present invention, and A-
This is a cross-sectional view taken along the line A. In the figure, 3 is an intermediate heat exchanger as in the conventional example, and 17 is a stand pipe for the intermediate heat exchanger 3, the lower end of which is fixed to a core support structure (not shown). 1
8 is a ball, and 19 is a holding N'? formed in an annular shape on the inner peripheral surface of the stand pipe. , 20a, and 20b are inclined surfaces of the holding groove 19, which intersect with the axial direction and have an upward slope of 45°.

上記ボール18は中間熱交換器3の据付時において、ス
タンドパイプの内周面の保持溝19の最下端に位置し、
中間熱交換器3の外周面と接触している。
When the intermediate heat exchanger 3 is installed, the ball 18 is located at the lowest end of the retaining groove 19 on the inner peripheral surface of the stand pipe,
It is in contact with the outer peripheral surface of the intermediate heat exchanger 3.

そこで原子炉の運転後e)液温上昇に伴なってボール1
8は保持溝19内を傾斜面20&、に沼って緩やかに上
列し、中間熱交換器3を拘束することは々い。
Therefore, after operation of the reactor e) Ball 1
The intermediate heat exchanger 3 is often restrained by being arranged in the retaining groove 19 on the inclined surface 20&.

上記中間熱交換器3とスタンドパ411フ0間隙及びボ
ール18の径を適切に設定することにより、中間熱交換
器3とスタンドパイプ17の半径方向相対変位を中間熱
交換器3とボール18が接触したまま吸収することがで
きる。
By appropriately setting the gap between the intermediate heat exchanger 3 and the stand pipe 411 and the diameter of the ball 18, the intermediate heat exchanger 3 and the ball 18 can control the relative displacement in the radial direction between the intermediate heat exchanger 3 and the stand pipe 17. Can be absorbed while in contact.

また、中間熱交換器3の上下方向変位に対しても拘束力
を中間熱交換器3に与えることなく、中間熱交換器3を
変位させることができる。
Further, even when the intermediate heat exchanger 3 is displaced in the vertical direction, the intermediate heat exchanger 3 can be displaced without applying a restraining force to the intermediate heat exchanger 3.

一方、地震入力に対しては、中間熱交換器の荷重を受け
たボール18は、傾斜面20a、20b金介してスタン
ドパイプ17に荷重を与える。このとき荷重は半径方向
荷重と軸方向スラスト荷重としてスタンドパイプ17に
伝えられ、スタンドパイプ17の軸方向剛性は十分病い
ため、中間熱交換器3は、その機構部において剛に支持
されることになる。
On the other hand, in response to an earthquake input, the ball 18 that has received the load of the intermediate heat exchanger applies a load to the stand pipe 17 via the inclined surfaces 20a and 20b. At this time, the load is transmitted to the stand pipe 17 as a radial load and an axial thrust load, and since the axial rigidity of the stand pipe 17 is sufficiently poor, the intermediate heat exchanger 3 is rigidly supported in its mechanism. Become.

第6図ないし第7図は本発明における第2の発明を示す
要部の縦断面図、及びB−B線断面図であシ、図におい
て3は中間熱交換器、5は炉心支持構造、17は第4図
、第5図に示す第1発明の保持溝19及びボール18を
有する中間熱交換器用スタンドパイプであるが、この部
分を単なるボール又は円弧ばねで構成してもよい。21
 a、21bは液中ダンパ’1 22a、22bはリン
ク機構23はボール若しくはローラー24はボール又は
ローラー23の保持装置、25は炉心支持構造5に設け
られた中間熱交換器3の貫通穴である。
6 and 7 are longitudinal sectional views and BB line sectional views of essential parts showing the second aspect of the present invention, in which 3 is an intermediate heat exchanger, 5 is a core support structure, Reference numeral 17 designates a stand pipe for an intermediate heat exchanger having the holding groove 19 and ball 18 of the first invention shown in FIGS. 4 and 5, but this portion may be constructed of a simple ball or an arcuate spring. 21
a, 21b are submerged dampers '1; 22a, 22b are link mechanisms 23, balls or rollers 24 are holding devices for the balls or rollers 23; 25 are through holes of the intermediate heat exchanger 3 provided in the core support structure 5. .

なお、上記炉心支持構造5は軸方向に対して4ヂの傾き
を有して設置されている。
Note that the core support structure 5 is installed with an inclination of 4 degrees with respect to the axial direction.

上記中間熱交換器3は据付時、ボール18を介してスタ
ンドパイプ17に挿通され、中間熱交換器3とボール≠
テ午苧ヂ18音は接触している。
When the intermediate heat exchanger 3 is installed, it is inserted into the stand pipe 17 via the ball 18, so that the intermediate heat exchanger 3 and the ball ≠
The 18 sounds of Tegoon are in contact.

そこで原子炉の運転後の液温上昇に伴ない、中間熱交換
器3の軸心の炉心からみた半径方向位置は変化しないの
に対して、炉心支持構造5の熱膨張により、貫通穴25
の軸心は外側にずれ、中間熱交換器3の軸心と相対変位
する。
Therefore, as the liquid temperature increases after the reactor is operated, the radial position of the axis of the intermediate heat exchanger 3 as seen from the core does not change, but due to thermal expansion of the core support structure 5, the through hole 25
The axis of the intermediate heat exchanger 3 is shifted outward and displaced relative to the axis of the intermediate heat exchanger 3.

上記相対変位は、ボールベアリング23が炉心支持構造
5の上面をガイド機構26に沼って滑ることにより吸収
し、スタンドパイプ17の炉心支持t?7造5に対する
拘束tf& tMである液中ダンパ21a。
The above relative displacement is absorbed by the ball bearing 23 sliding on the upper surface of the core support structure 5 against the guide mechanism 26, and the core support t? The submerged damper 21a is a restraint tf&tM for the structure 5.

21b1 リンク機構22a 、22bの部分においで
も、液中ダンパ21a、21bの相対運動により吸収す
ることができ、中間熱交換器3に拘束力を伺加しない。
21b1 Even in the link mechanisms 22a and 22b, it can be absorbed by the relative movement of the submerged dampers 21a and 21b, and no restraining force is applied to the intermediate heat exchanger 3.

ガイド機構26は断面が2型のレールをボルト27で炉
心支持構造5に固定する。
The guide mechanism 26 fixes a rail having a type 2 cross section to the core support structure 5 with bolts 27 .

一方地震入力に対しては、中間熱交換器3からボール1
8を介してスタンドパイプ17に伝えられた荷重は、ス
タンドパイプ17でスラスト荷重となってリンク機構2
08→液中ダンパ2 Q a−+20b−IJンク機構
20b−炉心支持構造5の順に伝えられるが、地震のよ
うに速い速度変化に対しては、液中ダンパ21bのオリ
フィスホールなどに生ずる圧損が、液中ダンパ21a、
21bとの相対速度の2乗に比例するので、大きな抗力
を生み、この機構部において、支持機能を有することに
なる。なお液中ダンパ21a、21b、 リンク機構2
2a、22bの機構は、周方向に複数体膜ければその効
果は更に増大する。
On the other hand, for earthquake input, from intermediate heat exchanger 3 to ball 1
The load transmitted to the stand pipe 17 via the link mechanism 2 becomes a thrust load in the stand pipe 17.
08→Liquid damper 2 Q a-+20b-IJ link mechanism 20b-core support structure 5, but in response to a fast speed change such as an earthquake, the pressure loss that occurs in the orifice hole of the liquid damper 21b is , submerged damper 21a,
Since it is proportional to the square of the relative speed with respect to 21b, it produces a large drag force, and this mechanism part has a supporting function. Note that the submerged dampers 21a and 21b, and the link mechanism 2
The effects of the mechanisms 2a and 22b will be further enhanced if a plurality of membranes are provided in the circumferential direction.

以上詳細に説明したように、本発明による原子炉内機器
の支持装置によれば、第1へ造が簡単であり、しかも制
振効果が犬であり、地N4時の径方向の急激な振動に対
しては大きな抗カケ生じさせるものである。
As explained in detail above, according to the support device for equipment in a nuclear reactor according to the present invention, the first structure is simple, the vibration damping effect is good, and the sudden vibration in the radial direction when the ground N4 is It causes a great deal of resistance to chipping.

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

第1図は従来の炉内機器支持第11造を示す縦断面図、
第2図は従来のマノメータ構造を示す横断面図、第3図
は第2図の縦1v+面図、21℃4図は本発明における
8p、1の発明を示す炉内機器の支持装置のれ・Y断面
図、第5図は第4図のA−A線断面図、第6図は本発明
における第2の発明を示す炉内機器の支持装置?)′の
縦11ツ1面図、第7図は第6図のB−B11・姐”す
11百1図である。 3・・・中間熱交換器、5・・・炉心支持構造、17・
・・スタンドパイプ、18・・・ボール、19・・・保
持溝、20 a 、 20 b・・・傾剃面、21 a
 、 2 l b−液中ダンパ、22a、22b・・・
リンク(−14、26・・・ガイド機構’l”# fr
′F出願人 三菱原子カニ業株式会社代理人 弁理土佐
 TI卜 英 昭 −)4−z (i) ぞす乙(い う7ml 手続補正書(自発) 1 事件の表示 昭和58年特 許 願第180751号2、発明の名称
 原子炉内機器の支持装置3、 補正をする者 41件との関係 %針山願人 住 所 東京都港区芝公園二丁目4香1号氏 名(名称
)(616)三菱原子カニ業株式会社4、代理人 5 補正命令の日イ、1 6 補正により増加する発明の数 図11色Q) t127図?別紙の辿り補正するう7(
Figure 1 is a vertical cross-sectional view showing the conventional equipment support structure No. 11;
Fig. 2 is a cross-sectional view showing the conventional manometer structure, Fig. 3 is a vertical 1v + side view of Fig. 2, and Fig. 4 at 21°C is a diagram of a support device for furnace equipment showing the invention of 8p, 1 in the present invention.・Y sectional view, FIG. 5 is a sectional view taken along the line A-A in FIG. )' is a vertical 11 side view, and Figure 7 is a B-B11/1101 view of Figure 6. 3...Intermediate heat exchanger, 5...Core support structure, 17・
... Stand pipe, 18... Ball, 19... Holding groove, 20 a, 20 b... Inclined shaved surface, 21 a
, 2lb-liquid damper, 22a, 22b...
Link (-14, 26...Guide mechanism 'l"# fr
'F Applicant Mitsubishi Atomic Crab Industry Co., Ltd. Agent Patent Attorney Tosa TI Boku Hideaki-) 4-z (i) Zosu Otsu (7ml) Procedural Amendment (Spontaneous) 1 Indication of Case 1980 Patent Application No. 180751 No. 2, Title of the invention Support device for internal reactor equipment 3 Relationship with 41 amendments by applicant % Hariyama Address 1, Shibakoen 2-4ka, Minato-ku, Tokyo Name (Name) (616) Mitsubishi Atomic Crab Industry Co., Ltd. 4, Agent 5 Date of amendment order A, 1 6 Number of inventions increased by amendment Figure 11 Color Q) t127 diagram? Correct the trace on the attached page 7 (
hill

Claims (1)

【特許請求の範囲】 (11炉内機器である被支持体の外側にスタンドパイプ
を設け、上記スタンドパイプの内周面に軸方向に対して
上向き傾斜を有する環状の保持溝全形成し、上記保持溝
内に被支持体と接触するボールを配設すると共に、上記
スタンドバイブ下端を炉心支持構造に固着したことを特
徴とする原子炉内機器の支持装置。 (2)前記上向き傾斜を有する環状の保持溝は、軸方向
に対する上向き傾斜が45度であることを特徴とする特
許請求の範囲第(1)項記載の原子炉内4vさ器の支持
装置〜。 (3)炉内機器である被支持体の外側にスタンドパイプ
を設り、上記スタンドパイプの内周面に軸方向に対して
土向き斜面ヲ有する環状の保持溝を形成し、上記保持溝
内KJI支持体と接触するボールを配設すると共に、上
記スタンドパイプは下端にボール若しくはローラー等の
転動体を内装した保持装置n介して炉心支持構造上の斜
面に配設し、かつ、上記スタンドパイプ上端と上記炉心
支持構造と’t IJンク機構を介して液中ダンパーに
て連結したことを%徴とする、原子炉内機器の支持装置
。 (4)前記上向き傾斜を有する環状の保持溝は、軸方向
に対する上向き傾斜が45度であるととを特徴とする特
許請求の範囲第(3)項記載の原子炉内機器の支持装置
道。
[Claims] (11) A stand pipe is provided on the outside of the supported body which is the furnace equipment, and an annular holding groove having an upward slope with respect to the axial direction is entirely formed on the inner circumferential surface of the stand pipe, A device for supporting equipment in a nuclear reactor, characterized in that a ball that contacts the supported body is disposed in a holding groove, and the lower end of the stand vibe is fixed to a core support structure. (2) The annular shape having an upward slope. A support device for a 4V vessel in a nuclear reactor according to claim (1), wherein the holding groove has an upward slope of 45 degrees with respect to the axial direction. (3) In-reactor equipment. A stand pipe is provided on the outside of the supported body, and an annular holding groove having an axially facing slope is formed on the inner circumferential surface of the stand pipe, and a ball is placed in the holding groove in contact with the KJI support body. At the same time, the standpipe is arranged on the slope above the core support structure via a holding device n having rolling elements such as balls or rollers at the lower end, and the upper end of the standpipe and the core support structure are connected to each other. A support device for equipment inside a nuclear reactor, which is connected by a submerged damper via an IJ link mechanism. (4) The annular holding groove having an upward slope has an upward slope of 45 mm with respect to the axial direction. A support device for equipment in a nuclear reactor according to claim (3), characterized in that:
JP58180751A 1983-09-30 1983-09-30 Supporter for apparatus in reactor Pending JPS6073393A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58180751A JPS6073393A (en) 1983-09-30 1983-09-30 Supporter for apparatus in reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58180751A JPS6073393A (en) 1983-09-30 1983-09-30 Supporter for apparatus in reactor

Publications (1)

Publication Number Publication Date
JPS6073393A true JPS6073393A (en) 1985-04-25

Family

ID=16088676

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58180751A Pending JPS6073393A (en) 1983-09-30 1983-09-30 Supporter for apparatus in reactor

Country Status (1)

Country Link
JP (1) JPS6073393A (en)

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