JPS6190092A - Parting device for well pool of nuclear reactor - Google Patents
Parting device for well pool of nuclear reactorInfo
- Publication number
- JPS6190092A JPS6190092A JP59211412A JP21141284A JPS6190092A JP S6190092 A JPS6190092 A JP S6190092A JP 59211412 A JP59211412 A JP 59211412A JP 21141284 A JP21141284 A JP 21141284A JP S6190092 A JPS6190092 A JP S6190092A
- Authority
- JP
- Japan
- Prior art keywords
- pool
- partition
- reactor well
- water
- spent fuel
- 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
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (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】
〔発明の技術分野〕
本発明は原子炉ウェルプールの仕切装置に係り、原子力
発電所における原子炉つLルプールと使用済燃料貯蔵プ
ールとの間、および原子炉ウェルプールと機器仮置貯蔵
プールとの間それぞれを、単独に、独自に水密的に閉塞
でき、それぞれのプールを単独に水張り可能となす原子
炉つ1ルプールの仕切装置に関するものである。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a partitioning device for a nuclear reactor well pool, and a device for partitioning between a reactor well pool and a spent fuel storage pool in a nuclear power plant. This invention relates to a partitioning device for a nuclear reactor pool, which can independently and independently watertightly close the space between the reactor and the temporary equipment storage pool, and each pool can be filled with water independently.
従来、原子力発電所の建設に際し、各プールの水張り漏
洩試験を実施するとぎの原子炉ウェルプールの仕切装置
は、第4図乃至第7図に示すように描成されていた。す
なわら、原子力発電所の原子炉建屋における原子炉ウェ
ルプールP1の両側に使用済燃料貯蔵プールP2、(大
器仮置貯蔵プールP3が配されており、原子炉ウェルプ
ールP1と使用済燃料貯蔵プールP2との間、原子炉ウ
ェルプールP1と機器仮置貯蔵プールP3との間に設け
られた仕切板13.16によって、使用済燃料貯蔵プー
ルP2、機器仮置貯蔵プールP3それぞれに水が張られ
ている。原子炉ウェルプールP1と使用済燃料貯蔵プー
ルP2との間に設【)た仕切板13によって両プールP
1.P2間は仕切られており、この仕切板13による仕
切区画方法は、第5図、第6図に示づよう記、水を張る
がわである使用済燃料貯蔵プールP2の壁面に一定の角
度を設けて取付けられている取付金具17に支持金物1
8を介して仕切板13を係合支持させると共に、仕切板
13自身の重量によってプール壁面にi 押し
付けられることで水密性が19られるようにすることに
よっている。そして、使用済燃料貯蔵ブールP2内に水
が張られ、水位が上背するに伴い、その水圧によってプ
ール壁面に押しf=jける力がhDねり密6麿が増すこ
とになる。その結果、使用’6%燃料貯蔵プールP2に
水を張っても原子炉・フェルプールP1がわには水が流
入せず、使用済燃料貯蔵プールP2の水張り漏洩試験を
行なうことができる。一方、機器仮置貯蔵プールP3に
J月ノる仕切板16による仕切区画方法についてもこれ
と全く同様である。そして、原子炉ウェルプールP1に
ついては、仕切板13.16を取外し各プールP2.P
3と同時に水張りを行なうことで、これの水張り漏洩試
験を行なうことができる。Conventionally, during the construction of a nuclear power plant, a partitioning device for a reactor well pool for carrying out a water filling leakage test for each pool has been drawn as shown in FIGS. 4 to 7. In other words, a spent fuel storage pool P2 and a (large temporary storage pool P3) are arranged on both sides of the reactor well pool P1 in the reactor building of a nuclear power plant, and the reactor well pool P1 and the spent fuel A partition plate 13.16 provided between the storage pool P2 and between the reactor well pool P1 and the temporary equipment storage pool P3 prevents water from flowing into the spent fuel storage pool P2 and the temporary equipment storage pool P3, respectively. A partition plate 13 installed between the reactor well pool P1 and the spent fuel storage pool P2 separates both pools P.
1. Space P2 is partitioned, and the partitioning method using this partition plate 13 is as shown in FIGS. 5 and 6. The support hardware 1 is attached to the mounting bracket 17 that is installed with the
The partition plate 13 is engaged and supported through the partition plate 8, and the partition plate 13 is pressed against the pool wall surface by its own weight, thereby achieving watertightness. Then, water is filled in the spent fuel storage boule P2, and as the water level rises, the force f=j pushing against the pool wall surface due to the water pressure increases. As a result, even if the 6% used fuel storage pool P2 is filled with water, water will not flow into the reactor/fer pool P1, making it possible to perform a water filling leak test on the spent fuel storage pool P2. On the other hand, the method of partitioning the equipment temporary storage pool P3 using the partition plate 16 is exactly the same. Then, for the reactor well pool P1, the partition plates 13.16 are removed, and each pool P2. P
By filling water at the same time as step 3, you can perform a water filling leak test.
ところが、このような従来の原子炉つIルプールの仕切
装置は次のような欠点があった。すなわち、原子炉ウェ
ルプールP1にのみ水を張ろうとしても、単独にこれを
行なうことができず、使用済燃料貯蔵プールP2、機器
仮]ご貯蔵ブールP3も同時に水張りをしなければなら
ないことであつlこ 。However, such conventional partitioning devices for nuclear reactors and I/L pools have the following drawbacks. In other words, even if you try to fill only the reactor well pool P1 with water, you cannot do this independently, and you will have to fill the spent fuel storage pool P2 and equipment storage boule P3 with water at the same time. Atsuko.
ところが、これらの三つのプールP1.P2゜P3は、
いずれも内面をステンレス鋼板にてコンクリート面に内
張りを施し、内張り工事実施後は水張り漏洩試験を行な
う必要があり、更に、この水張り漏洩試験後には、その
中に各種の設面を据付けなければならない。特に、使用
済燃料プールP2の中には多数の使用済燃料貯蔵ラック
Rを据付1ノなければならず、また、原子炉ウェルプー
ルP1は、その座部に原子炉圧力容器Bが据付けられる
から、その容器B内の機器据付も実施しておく必要があ
る。こうしたことから、各ブールP1゜P2.P3の工
事期間は相当に異なり、そのため、各々のブールPI、
P2.P3における水張り漏洩試験の実施可能時期にも
大幅な着が生じるものである。However, these three pools P1. P2゜P3 is
In both cases, the inner surface is lined with stainless steel plates on the concrete surface, and after the lining work is completed, it is necessary to perform a water leakage test, and furthermore, after this water leakage test, various construction surfaces must be installed inside. . In particular, a large number of spent fuel storage racks R must be installed in the spent fuel pool P2, and the reactor pressure vessel B is installed in the seat of the reactor well pool P1. It is also necessary to install the equipment in container B. From this, each Boolean P1゜P2. The construction period of P3 varies considerably and therefore each bool PI,
P2. There will also be a significant delay in the period when the water leakage test can be carried out in P3.
したがって、原子炉ウェルプールP1の水張り漏洩試験
実施時1!I]によって使用浩燃料貯蔵ブールP2及び
使用済燃わ1貯蔵ラツクR等の設置の据付は時期が大幅
に遅れ、また、各ブールPl、P2゜P3の完成時期が
原子炉つJルブールP1の作業工程に左右され、その調
整作業が複雑で茗しく繁雑になるものであった。この結
果、ひいては、原子炉建屋におtJる運転操作床面「の
完成時期が遅れ、原子力発電所全体の建設期間におりる
クリ=y−カルパスとなり、全体の建設期間が長期にお
よぶ主要な要因となっているものである。Therefore, when conducting a leakage test with water in the reactor well pool P1, 1! I], the installation of used fuel storage boule P2 and spent fuel 1 storage rack R, etc. was delayed significantly, and the completion time of each boule P1, P2, P3 was delayed from that of reactor J le boule P1. It depends on the work process, and the adjustment work is complicated, complicated, and complicated. As a result, the completion of the operation floor in the reactor building will be delayed, leading to a crisis during the entire construction period of the nuclear power plant, resulting in major major problems extending over a long period of time. This is a contributing factor.
本発明は、叙上の如き従来の諸事情に鑑みG1出された
ものであり、その目的とするところは、原子炉ウゴルプ
ール、使用済燃料貯蔵プール、機器仮置貯蔵プールそれ
ぞれを独自に水張り可能なものとし、単独で水張り漏洩
試験を実施できるものとして、工期の大幅な短縮、工数
の低減、作栗上の安全性向上、能率向上が図れる原子炉
ウェルプールの仕切装置を冑ることにある。The present invention was published in G1 in view of the conventional circumstances as described above, and its purpose is to independently fill the nuclear reactor pool, spent fuel storage pool, and equipment temporary storage pool with water. The objective is to develop a partition device for the reactor well pool that can significantly shorten the construction period, reduce man-hours, improve safety during chestnut production, and improve efficiency by making it possible to conduct water-filled leakage tests independently. .
上述した目的を達成するため、本発明にあっては、原子
力発電所における原子炉ウェルプールの両側に使用済燃
料貯蔵プールと機器仮置貯蔵プールとを配装し、原子炉
ウェルプールと使用済燃1ミ1貯蔵プールとの間、原子
炉ウェルプールと低器仮「9貯藏プールとの間をそれぞ
れ水密的に(」切る(]切装首に43いて、原子炉ウェ
ルプールと使・用済燃料貯蔵プールどの間、原子炉つ1
ルプールと機器仮置貯蔵プールとの間それぞれ設置ノら
れた連通水路に、この連通水路の断面に比し大きな断面
を有して形成された仕切ピッ1へと、この仕切ピットに
お()る各プールがわにある両取付面に設けられる取付
金具と、水張りさせるべきプールに対して少なくとも反
対がわの面にある取付金具に支持セラ1へ8れて、水張
りざけlこプールがわの水圧によって他方のプールがわ
の取付面に押し付けられることで連通水路を閉塞jる仕
り板とを猫えたことにγjするものである。In order to achieve the above-mentioned object, the present invention provides a spent fuel storage pool and a temporary equipment storage pool on both sides of a reactor well pool in a nuclear power plant. The reactor well pool and the low storage storage pool are watertightly cut (43) between the reactor well pool and the low storage storage pool. Between the fuel storage pool and the reactor
The communication waterway installed between the pool and the equipment temporary storage pool is connected to the partition pit 1 formed with a larger cross section than the cross section of the communication waterway. The mounting brackets provided on both mounting surfaces on each side of each pool and the mounting brackets on at least the opposite side of the pool to be filled with water are attached to the support cellar 1, so that the pool can be filled with water. In addition, the partition plate is pressed against the mounting surface of the other side of the pool by water pressure, thereby blocking the communicating waterway.
以下、第1図乃至第3図を参照して本発明の一実施例を
説明すると次の通りでおる。An embodiment of the present invention will be described below with reference to FIGS. 1 to 3.
図において示される符号P1は原子炉ウェルプールであ
り、この91両側に使用済燃料貯蔵ブーj ルP
2と機器仮置貯蔵プールP3とが配装されており、原子
炉ウェルプールP1と使用済燃料貯蔵プールP2との間
、原子炉ウェルプールP1と機器仮置貯蔵プールP3と
の間それぞれ設()られた連通水路1.4によって各プ
ールPi、P2あるいはPl、P3は相互に連通されて
いる。The symbol P1 shown in the figure is a reactor well pool, and spent fuel storage pools P1 are located on both sides of this 91 well pool.
2 and a temporary equipment storage pool P3 are installed between the reactor well pool P1 and the spent fuel storage pool P2, and between the reactor well pool P1 and the equipment temporary storage pool P3 ( ) The respective pools Pi, P2 or Pl, P3 are interconnected by a communicating waterway 1.4.
連通水路1,4それぞれには、ぞの略中央部にJ3いて
連通水路1,4の断面に比し大きな断面を右している仕
切ピット2.5が形成されている。A partition pit 2.5 is formed in each of the communicating waterways 1 and 4 at approximately the center thereof and has a larger cross section than the cross section of the communicating waterways 1 and 4.
ザなわら、図示のように、断面矩形Cある連通水路1.
4における深さ、幅員に比し、仕切ピッ[〜2.5にお
けるそれらは−回り人きいものとしてあり、連通水路1
,4の断面に比し大きな後述Jる仕切板3,6が仕切ピ
ット2,5に配されることで連通水路口1.4は閉塞さ
れるようになっている。As shown in the figure, a communicating waterway 1 with a rectangular cross section C.
Compared to the depth and width in 4, the partition pitches [~2.5] are as large as the width of the connecting waterway 1.
, 4 are arranged in the partition pits 2, 5, so that the communication waterway port 1.4 is closed off.
そして、仕切ピット2,5における各1−ル1〕1、P
2.、P3がわである両取付面に取付金具7を設りであ
る。この取付金具7は、従来と同様に、取付面に対し一
定の角度を設けて取り付けられてj3す、図示のように
、側面り字形にして、取付面における連通水路1,4開
口部分の両側、上下部に取り付けられている。すなわら
、取付金具7は、仕切ピット2にあっては、原子炉つ■
ルプールP1がね、使用済燃料貯蔵プールP2がねそれ
ぞれに、また、仕切ピット5にあっては、原子炉ウェル
プールP1がわ、機器仮置貯蔵ブールP3がわ(れぞれ
の取付面に配置されているのである。Then, each 1-rule 1] 1, P in the partition pits 2 and 5
2. , P3 is provided with mounting brackets 7 on both mounting surfaces. As in the past, this mounting bracket 7 is mounted at a certain angle to the mounting surface.As shown in the figure, the mounting bracket 7 is shaped like a side cursor, and is attached to both sides of the openings of the communication channels 1 and 4 on the mounting surface. , attached to the top and bottom. In other words, when the mounting bracket 7 is in the partition pit 2,
In addition, in the partition pit 5, the reactor well pool P1 and the equipment temporary storage boule P3 are attached to each mounting surface. It has been placed.
この取付金具7には、連通水路1.4の断面に比し大き
な断面を有する仕切板3,6の両側、上下部に突設した
支持金物8が係合されることで、仕切板3.6を支持さ
せるものとし、このとぎ、仕切板3,6は連通水路1,
4を閉塞すべく取付面に水密的に密着されるようになっ
ている。仕切板3は、11′切ピツト2において、使用
済燃料貯蔵ブールP2がわに水張りするときはこのプー
ルP2の反対がわにある原子炉ウェルプールP1がわの
取付面に支持される。また、仕切板6は、仕切ピット5
において、機器仮置貯蔵プールP3がわに水張りづるど
きはこのプールP3の反対がわにある原子炉ウェルプー
ルP1がわの取f4面に支持される。そして、原子炉ウ
ェルプールP1に水張りリ−るときに(、L、仕切ピッ
1−2においての仕切板3は使用済燃料貯蔵プールP2
がわの取付面に、また、仕切ピット5においての11切
仮6は機器仮置貯蔵プールP3がわの取イ]面にそれぞ
れ支持される。このように、水張り寸べきプールP1.
P2、P3によって、仕切板3.6は仕切ピット2゜5
における取付面を変更し、それの反対がゎの取付面を選
択してそこに支持されるものである。Support metal fittings 8 protruding from both sides, upper and lower parts of the partition plates 3 and 6, which have a larger cross section than the cross section of the communication waterway 1.4, are engaged with the mounting fittings 7, so that the partition plates 3. At this point, the partition plates 3 and 6 are used to support the communication waterways 1 and 6.
4, so as to close the mounting surface in a watertight manner. The partition plate 3 is supported by the mounting surface of the reactor well pool P1 on the opposite side of the spent fuel storage boule P2 in the 11' cut pit 2 when the spent fuel storage boule P2 is filled with water. In addition, the partition plate 6 is connected to the partition pit 5.
In this case, the equipment temporary storage pool P3 filled with water is supported by the handle f4 of the reactor well pool P1, which is located on the opposite side of this pool P3. When the reactor well pool P1 is filled with water (L, the partition plate 3 at the partition pit 1-2 is
The 11 cutouts 6 in the partition pit 5 are supported on the mounting surface of the gutter, and the 11 cutouts 6 in the partition pit 5 are supported on the mounting surface of the gauve of the equipment temporary storage pool P3. In this way, the pool P1 which should be filled with water.
By P2 and P3, the partition plate 3.6 is divided into a partition pit 2°5
Change the mounting surface in , and select the mounting surface in ゎ for the opposite of that, and it will be supported there.
なお、仕切板3.6を仕切ピット2,5におtプる両取
付面にそれぞれ支持セラ1−させておくもよく、この場
合は、仕切板3.6の支持位首を変更させずとも、各プ
ールP1.P2.P3それぞれに独自に水張りを行なう
ことができる。In addition, it is also possible to have support plates 1- on both mounting surfaces of the partition plates 3.6 to the partition pits 2 and 5. In this case, the support positions of the partition plates 3.6 should not be changed. Also, each pool P1. P2. Each P3 can be filled with water independently.
本発明はJス−Fのように、原子かつlルプールと使用
済E料貯蔵プールとの聞、原子炉ウェルプールと機器仮
置貯蔵プールとの間ぞれぞれに8Ωりられた連通水路に
仕切ピットを形成し、この仕切ピットにお1ノる両取付
而に取イNJ金具を設けてJ3さ、水張りさせるべきプ
ールに対応して仕切板の取(=J金具を介しての取f1
面をその反λ・1がねとして選択することで仕切板を支
持させるから、水張りしたプールの水圧によって他方の
プールがねへ佳り板を押し付【プ、連通水路を閉塞でき
るものとなり、そのため、原子炉ウェルプール、使用済
燃料貯蔵プール、機器仮置貯蔵プールそれぞれに独自に
水張りを行なうことができる。そのため、原子炉ウェル
プールの水張りを単独に行なうことができ、使用済燃料
貯蔵プール、機器仮置貯蔵プール内のステンレス鋼板内
張工事、内部機器据付作業と、原子炉ウェルプールの水
張り漏洩試験とを各々別個に実施することが可能である
。その結果、大幅に工程が短縮されるから、作業上の繁
雑性が改善され、作業効率を大きく向上できるものであ
る。The present invention, like the JS-F, provides a communication waterway with an 8Ω resistance between the atomic reactor well pool and the spent E material storage pool, and between the reactor well pool and the equipment temporary storage pool. A partition pit is formed in the partition pit, and NJ fittings are installed on both sides of the partition pit to attach the partition plate (= installation via the J fittings) corresponding to the pool to be filled with water. f1
Since the partition plate is supported by selecting the surface as the anti-λ・1 angle, the water pressure of the filled pool can push the partition plate against the other pool and block the communicating waterway. Therefore, the reactor well pool, spent fuel storage pool, and equipment temporary storage pool can each be filled with water independently. Therefore, the reactor well pool can be filled with water independently, and can be used for lining the spent fuel storage pool and equipment temporary storage pool with stainless steel plates, internal equipment installation work, and filling the reactor well pool with water for leakage tests. It is possible to perform each separately. As a result, the process is significantly shortened, the complexity of the work is improved, and the work efficiency can be greatly improved.
したがって、これらの種々の効果の総合によって、原子
力発電所建設工期の大幅な短縮と費用の部約とは著しい
ものである等の優れた点が認められるのである。Therefore, by combining these various effects, it is recognized that there are excellent points such as a significant reduction in the construction period of a nuclear power plant and a significant reduction in costs.
第1図乃至第3図は本発明の一実施例を示し、第1図は
平面図、第2図は要部平面図、第3目1は要部断側面図
であり、第4図乃〒第7図は従来例を示し、その第4図
は断面図、第5図は第4図(二J3LJ8V −V線矢
視平面図、第6図は第5図のΔ部拡大平面図、第7図は
第6図にJ月)るv■−■線矢’f’>1g7i面図で
ある。
Pl・・・原子炉ウェルプール、P2・・・使用済燃料
貯蔵プール、P3・・・様器仮置貯蔵プール、B・・・
原子炉圧力容器、R・・・使用済燃料貯蔵ラック、「・
・・運転操作床面、1・・・連通水路、2・・・11切
ビツト、3・・・仕切板、4・・・連通水路、5・・・
仕切ビット、6・・・仕切板、7・・・取1τ1金具、
8・・・支持金物、13・・・仕切板、16・・・仕切
板、17・・・取付金具、18・・・支持金物。1 to 3 show an embodiment of the present invention, FIG. 1 is a plan view, FIG. 2 is a plan view of the main part, 3rd item 1 is a sectional side view of the main part, and FIGS. 〒FIG. 7 shows a conventional example, FIG. 4 is a sectional view, FIG. 5 is a plan view of FIG. FIG. 7 is a plane view of v■-■ line arrow 'f'>1g7i shown in FIG. Pl... Reactor well pool, P2... Spent fuel storage pool, P3... Temporary vessel storage pool, B...
Reactor pressure vessel, R...Spent fuel storage rack,
...Operation floor surface, 1...Communicating waterway, 2...11 cut bits, 3...Partition plate, 4...Communicating waterway, 5...
Partition bit, 6... Partition plate, 7... Take 1τ1 metal fitting,
8... Support hardware, 13... Partition plate, 16... Partition plate, 17... Mounting hardware, 18... Support hardware.
Claims (1)
使用済燃料貯蔵プールと機器仮置貯蔵プールとを配装し
、原子炉ウェルプールと使用済燃料貯蔵プールとの間、
原子炉ウェルプールと機器仮置貯蔵プールとの間をそれ
ぞれ水密的に仕切る仕切装置において、原子炉ウェルプ
ールと使用済燃料貯蔵プールとの間、原子炉ウェルプー
ルと機器仮置貯蔵プールとの間それぞれに設けられた連
通水路に、この連通水路の断面に比し大きな断面を有し
て形成された仕切ピットと、この仕切ピットにおける各
プールがわにある両取付面に設けられる取付金具と、水
張りさせるべきプールに対して少なくとも反対がわの面
にある取付金具に支持セットされて、水張りさせたプー
ルがわの水圧によって他方のプールがわの取付面に押し
付けられることで連通水路を閉塞する仕切板とを備えた
ことを特徴とする原子炉ウェルプールの仕切装置。 2、仕切板は、仕切ピットにおける両取付面それぞれに
支持セットされている特許請求の範囲第1項記載の原子
炉ウェルプールの仕切装置。[Claims] 1. A spent fuel storage pool and an equipment temporary storage pool are arranged on both sides of a reactor well pool in a nuclear power plant, and between the reactor well pool and the spent fuel storage pool,
Between the reactor well pool and the spent fuel storage pool, and between the reactor well pool and the equipment temporary storage pool, in a partition device that watertightly partitions the reactor well pool and the equipment temporary storage pool. A partition pit formed in each of the communicating waterways with a cross section larger than the cross section of the communicating waterway, and mounting brackets provided on both mounting surfaces of each pool in the partition pit, It is supported and set on a mounting bracket on at least the opposite side of the pool to be filled with water, and the water pressure of the filled pool presses the other pool against the mounting surface of the other pool, thereby blocking the communication waterway. A partition device for a nuclear reactor well pool, characterized by comprising a partition plate. 2. The reactor well pool partition device according to claim 1, wherein the partition plate is supported and set on each of both mounting surfaces in the partition pit.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59211412A JPS6190092A (en) | 1984-10-11 | 1984-10-11 | Parting device for well pool of nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59211412A JPS6190092A (en) | 1984-10-11 | 1984-10-11 | Parting device for well pool of nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6190092A true JPS6190092A (en) | 1986-05-08 |
Family
ID=16605525
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP59211412A Pending JPS6190092A (en) | 1984-10-11 | 1984-10-11 | Parting device for well pool of nuclear reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6190092A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6141171A (en) * | 1997-04-28 | 2000-10-31 | Nec Corporation | Cue signal detection circuit of magnetic recording and reproducing device |
-
1984
- 1984-10-11 JP JP59211412A patent/JPS6190092A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6141171A (en) * | 1997-04-28 | 2000-10-31 | Nec Corporation | Cue signal detection circuit of magnetic recording and reproducing device |
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