JPS5952797B2 - Reactor core emergency cooling system - Google Patents
Reactor core emergency cooling systemInfo
- Publication number
- JPS5952797B2 JPS5952797B2 JP52064145A JP6414577A JPS5952797B2 JP S5952797 B2 JPS5952797 B2 JP S5952797B2 JP 52064145 A JP52064145 A JP 52064145A JP 6414577 A JP6414577 A JP 6414577A JP S5952797 B2 JPS5952797 B2 JP S5952797B2
- Authority
- JP
- Japan
- Prior art keywords
- pipe
- water
- reactor core
- cooling system
- fuel element
- 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
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)
Description
【発明の詳細な説明】 本発明は原子炉炉心緊急冷却装置に係る。[Detailed description of the invention] The present invention relates to a nuclear reactor core emergency cooling system.
沸騰水型原子炉において、冷却材喪失事故時に、燃料集
合体を緊急冷却する装置は、通常下記の如く構成されて
いる。In a boiling water reactor, a device for emergency cooling of a fuel assembly in the event of a loss of coolant accident is usually configured as follows.
すなわち、第1図に示すように炉心1を収容する圧力容
器2内に、炉心1上方に位置してリング状の配水管3を
設け、この配管に円周方向に分布して複数箇のスプレィ
ノズル4を設けて緊急冷却装置を構成している。That is, as shown in FIG. 1, a ring-shaped water distribution pipe 3 is provided in a pressure vessel 2 housing a reactor core 1 above the reactor core 1, and a plurality of spray pipes are distributed in the circumferential direction on this pipe. A nozzle 4 is provided to constitute an emergency cooling device.
事故発生時には、スプレィノズル4から冷却水を噴霧す
る。When an accident occurs, cooling water is sprayed from the spray nozzle 4.
この水は燃料要素上部タイプレート流水孔から燃料要素
内に流入し燃料要素の冷却を行う。This water flows into the fuel element from the fuel element upper tie plate water flow hole and cools the fuel element.
ところがこのような従来の装置にあっては、すでに燃料
要素内に流入し冷却に関与した冷却水が蒸気となって燃
料要素内を上昇して来るので、冷却水がそれに吹上げら
れ燃料要素内に流入し難い欠点があった。However, in such conventional devices, the cooling water that has already flowed into the fuel element and participated in cooling turns into steam and rises inside the fuel element, so the cooling water is blown up and flows into the fuel element. There was a drawback that it was difficult to get into the market.
また、燃料要素の上部タイプレートの流水孔は比較的小
さなものなので、ノズルから噴射された冷却水はタイプ
レート上に−たん貯溜され、流水孔から自然流下して燃
料要素内に流入することとなり、ノズルから噴出した冷
却水が持っている速度エネルギは全く利用されていない
。In addition, since the water flow holes in the upper tie plate of the fuel element are relatively small, the cooling water injected from the nozzle is stored on the tie plate and naturally flows down from the water flow holes and flows into the fuel element. , the velocity energy of the cooling water spouted from the nozzle is not utilized at all.
前記の速度エネルギを利用することができれば、従来装
置より大量の冷却水を燃料要素内に流入させ得る筈であ
る。If such velocity energy could be utilized, a larger amount of cooling water could be allowed to flow into the fuel element than in conventional systems.
本発明は上記の事情に鑑みなされたもので、冷却材喪失
事故時に燃料要素内に速かに大量の水を注入することが
できる緊急冷却装置を提供する。The present invention has been made in view of the above circumstances, and provides an emergency cooling system that can quickly inject a large amount of water into a fuel element in the event of a loss of coolant accident.
以下図面につき本発明の詳細な説明する。The invention will now be described in detail with reference to the drawings.
第1図と同一部分には同一符号を附した第2図は本発明
一実施例の全体概略図であり、この図において各燃料要
素5の操作用ハンドル6は、矩形枠状を呈し第3図に示
す如く中空とされ、このハンドル6にはそのタイプレー
トに接する部材に燃料要素上部タイプレート7の流水孔
8の中、適当な間較の配置となるような選択した複数箇
の流水孔に開口された複数の分岐ノズル9が設けられて
いる。FIG. 2, in which the same parts as in FIG. The handle 6 is hollow as shown in the figure, and the handle 6 has a plurality of water flow holes selected from the water flow holes 8 of the upper tie plate 7 of the fuel element at suitable intervals in the member that contacts the tie plate. A plurality of branch nozzles 9 are provided.
燃料要素5を例えば第4図に示すように隣接するm箇宛
の群に分ち、群内の各燃料要素のハンドル6の給水管1
0とそれらの上方に配置された四分枝管11の各分岐と
を可撓性配管12で接続する。For example, as shown in FIG. 4, the fuel elements 5 are divided into m adjacent groups, and the water supply pipe 1 of the handle 6 of each fuel element in the group is
0 and each branch of the four-branch pipe 11 arranged above them are connected by a flexible pipe 12.
四分枝管11の本管は前記燃料要素の群の配置に対応し
てリング状配水管3に格子状に設けた配管13に垂下さ
せた分岐14と接続する。The main pipe of the four-branch pipe 11 is connected to a branch 14 which is suspended from a pipe 13 provided in a grid pattern in the ring-shaped water pipe 3 in accordance with the arrangement of the groups of fuel elements.
なお、図中、15,16.17は各接続部に使用される
継手を示し、望ましくは操作の簡単なワンタッチ継手と
する。In the figure, numerals 15, 16, and 17 indicate joints used for each connection, preferably one-touch joints that are easy to operate.
なお、第4図において18は給水管を示す。In addition, in FIG. 4, 18 indicates a water supply pipe.
上記構成の本発明装置においては、給水管18から供給
された冷却水はリング状配水管3がらその格子状配管1
3を経由し、分岐14から四分枝管11本管、その各分
岐、可撓性配管、バンドル6、分岐ノズル9を経由して
流水口8から燃料要素5内に送込まれる。In the apparatus of the present invention having the above configuration, the cooling water supplied from the water supply pipe 18 is transferred from the ring-shaped water pipe 3 to the lattice-shaped pipe 1.
The fuel is fed into the fuel element 5 from the water outlet 8 via the branch 14, the four-branch pipe 11 main pipe, each branch thereof, the flexible pipe, the bundle 6, and the branch nozzle 9.
上記の如く、冷却水はタイブレーI・上に−たん貯溜さ
れることなく、速度エネルギを保有したまま流水孔から
送込まれるので、燃料要素内を吹上げて来る蒸気に妨げ
られることなく燃料要素内に流入することができる。As mentioned above, the cooling water is not stored on the tiebrae I, but is sent through the water flow hole while retaining its velocity energy, so it is not hindered by the steam blowing up inside the fuel element. can flow inside.
従って、緊急時に大量の冷却水を燃料要素内に流入させ
ることができる。Therefore, a large amount of cooling water can flow into the fuel element in an emergency.
なお、本発明においては、操作用バンドルを中空とし、
これを燃料要素に冷却水を流入させるためのヘッダとし
て使用しているので、本発明による炉心上部の配管の増
加が最小限ですむ。In addition, in the present invention, the operating bundle is hollow,
Since this is used as a header for allowing cooling water to flow into the fuel element, the increase in piping in the upper part of the core according to the present invention can be minimized.
また、バンドルと上部タイプレートとを一体化したユニ
ツI・とじて作ることができ、この場合には炉心の組立
が容易化される。In addition, the bundle and the upper tie plate can be made into a unit by combining them together, and in this case, assembly of the core is facilitated.
さらに、四分枝管の分岐とバンドルとの接続に可撓性配
管を使用し、また各接続継手にワンタッチ継手を使用し
ているので、組立は容易となり組立時間は著しく短縮さ
れる。Furthermore, since flexible piping is used to connect the branch of the four-branch pipe and the bundle, and a one-touch joint is used for each connection joint, assembly is easy and the assembly time is significantly shortened.
第5図は前記実施例の変形例を示している。FIG. 5 shows a modification of the above embodiment.
この変形例では、バンドル6は中空で逆U字状とされ、
両側脚下端においてタイプレート7の適宜流水孔8と接
続され、中央片中央下面にはスプレーノズル19が設け
られている。In this modification, the bundle 6 is hollow and shaped like an inverted U,
The lower ends of both legs are connected to appropriate water holes 8 of the tie plate 7, and a spray nozzle 19 is provided on the lower surface of the center piece.
この変形例では、バンドル6の両側脚から燃料要素内に
速度エネルギを保有したまま冷却水が直接に送込まれる
と同時に、ノズル20からのスプレーがタイプレートの
流水孔8からも流入し、従来のリング状配水管からのス
プレーによるものよりも大量の冷却水を燃料要素内に送
込むことができる。In this modification, the cooling water is directly fed into the fuel element from both legs of the bundle 6 while retaining velocity energy, and at the same time, the spray from the nozzle 20 also flows through the water flow hole 8 of the tie plate. A larger amount of cooling water can be delivered into the fuel element than by spraying from a ring-shaped water pipe.
第1図は従来の緊急冷却装置を示す概略図、第2図は本
発明一実施例の概略図、第3図Aは本発明実施例要部の
断面図、同図Bはその斜視図、第4図は前記実施例全体
の斜視図、第5図は前記実施例の変形例要部の斜視図で
ある。
3・・・・・・リング状配水管、5・・・・・・燃料要
素、6・・・・・・操作用バンドル、7・・・・・・上
部タイプレート、8・・・・・・流水孔、9・・・・・
・分岐ノズル、11・・・・・・四分枝管、13・・・
・・・格子状配管。Fig. 1 is a schematic diagram showing a conventional emergency cooling device, Fig. 2 is a schematic diagram of an embodiment of the present invention, Fig. 3A is a sectional view of the main part of the embodiment of the present invention, and Fig. 3B is a perspective view thereof. FIG. 4 is a perspective view of the entire embodiment, and FIG. 5 is a perspective view of essential parts of a modification of the embodiment. 3... Ring-shaped water pipe, 5... Fuel element, 6... Operation bundle, 7... Upper tie plate, 8...・Water hole, 9...
・Branch nozzle, 11... Quadrant pipe, 13...
...Grid piping.
Claims (1)
燃料要素上端に設けられた中空の操作用ハンドル Cこのハンドル内中空部から燃料要素上部タイプレート
の複数の流水孔に開口する分岐ノズルd 燃料要素を隣
接する複数箇宛の群に分ち、各群内の燃料要素のハンド
ルを一括して前記配水管に接続する分岐管 2 前記分岐管と各操作用ハンドルとの接続をワンタッ
チ継手および可撓性配管によって行ったことを特徴とす
る特許請求の範囲第1項記載の原子炉炉心緊急冷却装置
。[Scope of Claims] 1. A nuclear reactor core emergency cooling system having the following structural requirements. a Water pipe provided in the upper part of the reactor core to provide cooling water b Hollow operation handle provided at the upper end of each fuel element C Branch nozzle d that opens from the hollow part inside this handle to multiple water flow holes in the upper tie plate of the fuel element A branch pipe 2 that divides the fuel elements into groups destined for a plurality of adjacent locations and connects the handles of the fuel elements in each group to the water distribution pipe at once.The branch pipe and each operation handle are connected by a one-touch joint and The emergency cooling system for a nuclear reactor core according to claim 1, characterized in that the emergency cooling system is implemented by a flexible pipe.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP52064145A JPS5952797B2 (en) | 1977-05-31 | 1977-05-31 | Reactor core emergency cooling system |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP52064145A JPS5952797B2 (en) | 1977-05-31 | 1977-05-31 | Reactor core emergency cooling system |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS53148694A JPS53148694A (en) | 1978-12-25 |
JPS5952797B2 true JPS5952797B2 (en) | 1984-12-21 |
Family
ID=13249606
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP52064145A Expired JPS5952797B2 (en) | 1977-05-31 | 1977-05-31 | Reactor core emergency cooling system |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS5952797B2 (en) |
Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
SE424931B (en) * | 1980-12-19 | 1982-08-16 | Asea Atom Ab | FUEL CARTRIDGE WITH WATER DISTRIBUTION CLEANER |
JPS58100784A (en) * | 1981-12-10 | 1983-06-15 | 株式会社東芝 | Reactor core spray device |
JPS59163594A (en) * | 1983-03-09 | 1984-09-14 | 株式会社日立製作所 | Emergency core cooling system |
CN111554425B (en) * | 2020-05-15 | 2022-02-11 | 中国核动力研究设计院 | Method for coping with extremely-small-break water loss accident of pressurized water reactor nuclear power plant |
-
1977
- 1977-05-31 JP JP52064145A patent/JPS5952797B2/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
JPS53148694A (en) | 1978-12-25 |
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